diff --git a/.gitignore b/.gitignore index fcb3136114..9089cb2518 100644 --- a/.gitignore +++ b/.gitignore @@ -49,6 +49,7 @@ dist/* documentation/io/vardes.md lcov_results/ env/ +env_process/ .venv *.DAT !scenario_examples/*/*.DAT diff --git a/process/data_structure/stellarator_variables.py b/process/data_structure/stellarator_variables.py index 91891a7e41..f631647d96 100644 --- a/process/data_structure/stellarator_variables.py +++ b/process/data_structure/stellarator_variables.py @@ -1,15 +1,24 @@ # These variables were from stellarator.f90 -f_n: float = None +f_st_n_coils: float = None +"""Actual number of coils to reference value from stella_config file""" -f_r: float = None +f_st_rmajor: float = None +"""Actual major radius to reference value from stella_config file""" -f_aspect: float = None +f_st_aspect: float = None +"""Actual aspect ratio to reference value from stella_config file""" -f_b: float = None +f_st_coil_aspect: float = None +"""Scaling factor for (stellarator major radius / coil radius ratio)""" -f_i: float = None +f_st_b: float = None +"""Actual b_plasma_toroidal_on_axis to reference value from stella_config file """ -f_a: float = None +f_st_i_total: float = None +"""Actual total coil current to reference value from stella_config file""" + +f_st_rminor: float = None +"""Actual minor radius to reference value from stella_config file""" first_call: bool = None @@ -97,16 +106,17 @@ def init_stellarator_variables(): global \ first_call, \ first_call_stfwbs, \ - f_n, \ - f_r, \ - f_a, \ - f_b, \ - f_i, \ + f_st_n_coils, \ + f_st_rmajor, \ + f_st_rminor, \ + f_st_b, \ + f_st_i_total, \ istell, \ bmn, \ f_asym, \ f_rad, \ f_w, \ + f_st_coil_aspect, \ fdivwet, \ flpitch, \ hportamax, \ @@ -127,11 +137,11 @@ def init_stellarator_variables(): first_call = True first_call_stfwbs = True - f_n = 0.0 - f_r = 0.0 - f_a = 0.0 - f_b = 0.0 - f_i = 0.0 + f_st_n_coils = 0.0 + f_st_rmajor = 0.0 + f_st_rminor = 0.0 + f_st_b = 0.0 + f_st_i_total = 0.0 istell = 0 bmn = 1e-3 f_asym = 1.0 @@ -143,7 +153,7 @@ def init_stellarator_variables(): hportpmax = 0.0 hporttmax = 0.0 iotabar = 1.0 - isthtr = 3 + isthtr = 1 m_res = 5 n_res = 5 shear = 0.5 diff --git a/process/init.py b/process/init.py index 07f7517419..64ec0d08a5 100644 --- a/process/init.py +++ b/process/init.py @@ -59,7 +59,7 @@ from process.exceptions import ProcessValidationError from process.input import parse_input_file from process.log import logging_model_handler -from process.stellarator import stinit +from process.stellarator.initialization import st_init def init_process(): @@ -86,7 +86,7 @@ def init_process(): set_device_type() # Initialise the Stellarator - stinit() + st_init() # Check input data for errors/ambiguities check_process(inputs) diff --git a/process/input.py b/process/input.py index 24e814c5c8..a286a478ff 100644 --- a/process/input.py +++ b/process/input.py @@ -707,6 +707,9 @@ def __post_init__(self): data_structure.tfcoil_variables, float, range=(0.0, 1.0) ), "f_w": InputVariable(data_structure.stellarator_variables, float, range=(0.1, 1.0)), + "f_st_coil_aspect": InputVariable( + data_structure.stellarator_variables, float, range=(0.1, 10.0) + ), "f_z_cryostat": InputVariable( data_structure.build_variables, float, range=(2.0, 10.0) ), diff --git a/process/iteration_variables.py b/process/iteration_variables.py index e2edaaf1f6..edafcdbbd6 100644 --- a/process/iteration_variables.py +++ b/process/iteration_variables.py @@ -288,6 +288,9 @@ class IterationVariable: ), 174: IterationVariable("triang", data_structure.physics_variables, 0.00, 1.00), 175: IterationVariable("kappa", data_structure.physics_variables, 0.00, 10.00), + 176: IterationVariable( + "f_st_coil_aspect", data_structure.stellarator_variables, 0.70, 1.30 + ), } diff --git a/process/main.py b/process/main.py index 9dc607dfb6..75e1d1e8b0 100644 --- a/process/main.py +++ b/process/main.py @@ -101,8 +101,9 @@ from process.pulse import Pulse from process.resistive_tf_coil import AluminiumTFCoil, CopperTFCoil, ResistiveTFCoil from process.scan import Scan +from process.stellarator.neoclassics import Neoclassics +from process.stellarator.stellarator import Stellarator from process.shield import Shield -from process.stellarator import Neoclassics, Stellarator from process.structure import Structure from process.superconducting_tf_coil import SuperconductingTFCoil from process.tf_coil import TFCoil @@ -689,18 +690,20 @@ def __init__(self): plasma_profile=self.plasma_profile, ) self.neoclassics = Neoclassics() - self.stellarator = Stellarator( - availability=self.availability, - buildings=self.buildings, - vacuum=self.vacuum, - costs=self.costs, - power=self.power, - plasma_profile=self.plasma_profile, - hcpb=self.ccfe_hcpb, - current_drive=self.current_drive, - physics=self.physics, - neoclassics=self.neoclassics, - ) + if data_structure.stellarator_variables.istell != 0: + self.stellarator = Stellarator( + availability=self.availability, + buildings=self.buildings, + vacuum=self.vacuum, + costs=self.costs, + power=self.power, + plasma_profile=self.plasma_profile, + hcpb=self.ccfe_hcpb, + current_drive=self.current_drive, + physics=self.physics, + neoclassics=self.neoclassics, + ) + self.dcll = DCLL(fw=self.fw) @property diff --git a/process/profiles.py b/process/profiles.py index c86714c2f7..db0a45cc4c 100644 --- a/process/profiles.py +++ b/process/profiles.py @@ -310,6 +310,7 @@ def calculate_profile_y( logger.info( f"TPROFILE: temperature pedestal is higher than core temperature. {temp_plasma_pedestal_kev = }, {t0 = }" ) + rho_index = rho <= radius_plasma_pedestal_temp_norm self.profile_y[rho_index] = ( temp_plasma_pedestal_kev diff --git a/process/stellarator.py b/process/stellarator.py deleted file mode 100644 index eb955acb7e..0000000000 --- a/process/stellarator.py +++ /dev/null @@ -1,5878 +0,0 @@ -import logging -from copy import copy -from pathlib import Path - -import numpy as np - -import process.fusion_reactions as reactions -import process.physics_functions as physics_funcs -import process.superconductors as superconductors -from process import constants -from process import process_output as po -from process.coolprop_interface import FluidProperties -from process.data_structure import ( - build_variables, - constraint_variables, - cost_variables, - current_drive_variables, - divertor_variables, - fwbs_variables, - global_variables, - heat_transport_variables, - impurity_radiation_module, - neoclassics_variables, - numerics, - pfcoil_variables, - physics_variables, - rebco_variables, - stellarator_configuration, - stellarator_variables, - structure_variables, - superconducting_tf_coil_variables, - tfcoil_variables, - times_variables, -) -from process.exceptions import ProcessValueError -from process.physics import rether -from process.stellarator_config import load_stellarator_config - -logger = logging.getLogger(__name__) - -# NOTE: a different value of electron_charge was used in the original implementation -# making the post-Python results slightly different. As a result, there is a -# relative tolerance on the neoclassics tests of 1e-3 -KEV = 1e3 * constants.ELECTRON_CHARGE # Kiloelectron-volt (keV) - - -class Stellarator: - """Module containing stellarator routines - author: P J Knight, CCFE, Culham Science Centre - N/A - This module contains routines for calculating the - parameters of the first wall, blanket and shield components - of a fusion power plant. - - """ - - def __init__( - self, - availability, - vacuum, - buildings, - costs, - power, - plasma_profile, - hcpb, - current_drive, - physics, - neoclassics, - ) -> None: - """Initialises the Stellarator model's variables - - :param availability: a pointer to the availability model, allowing use of availability's variables/methods - :type availability: process.availability.Availability - :param buildings: a pointer to the buildings model, allowing use of buildings's variables/methods - :type buildings: process.buildings.Buildings - :param Vacuum: a pointer to the vacuum model, allowing use of vacuum's variables/methods - :type Vacuum: process.vacuum.Vacuum - :param costs: a pointer to the costs model, allowing use of costs' variables/methods - :type costs: process.costs.Costs - :param plasma_profile: a pointer to the plasma_profile model, allowing use of plasma_profile's variables/methods - :type plasma_profile: process.plasma_profile.PlasmaProfile - :param hcpb: a pointer to the ccfe_hcpb model, allowing use of ccfe_hcpb's variables/methods - :type hcpb: process.hcpb.CCFE_HCPB - :param current_drive: a pointer to the CurrentDrive model, allowing use of CurrentDrives's variables/methods - :type current_drive: process.current_drive.CurrentDrive - :param physics: a pointer to the Physics model, allowing use of Physics's variables/methods - :type physics: process.physics.Physics - :param neoclassics: a pointer to the Neoclassics model, allowing use of neoclassics's variables/methods - :type neoclassics: process.stellarator.Neoclassics - """ - - self.outfile: int = constants.NOUT - self.first_call_stfwbs = True - - self.availability = availability - self.buildings = buildings - self.vacuum = vacuum - self.costs = costs - self.power = power - self.plasma_profile = plasma_profile - self.hcpb = hcpb - self.current_drive = current_drive - self.physics = physics - self.neoclassics = neoclassics - - def run(self, output: bool): - """Routine to call the physics and engineering modules - relevant to stellarators - author: P J Knight, CCFE, Culham Science Centre - author: F Warmer, IPP Greifswald - - This routine is the caller for the stellarator models. - - :param output: indicate whether output should be written to the output file, or not - :type output: boolean - """ - - if output: - self.costs.run() - self.costs.output() - self.availability.run(output=True) - self.physics.calculate_effective_charge_ionisation_profiles() - self.physics.outplas() - self.stheat(True) - self.stphys(True) - self.stopt(True) - - # As stopt changes nd_plasma_electrons_vol_avg, te and b_plasma_toroidal_on_axis, stphys needs two calls - # to correct for larger changes (it is only consistent after - # two or three fix point iterations) call stphys here again, just to be sure. - # This can be removed once the bad practice in stopt is removed! - self.stphys(False) - - self.stdiv(True) - self.stbild(True) - self.stcoil(True) - self.ststrc(True) - self.stfwbs(True) - - self.power.tfpwr(output=True) - self.buildings.run(output=True) - self.vacuum.run(output=True) - self.power.acpow(output=True) - self.power.output_plant_electric_powers() - - return - - self.stnewconfig() - self.stgeom() - self.stphys(False) - self.stopt(False) - self.stcoil(False) - self.stbild(False) - self.ststrc(False) - self.stfwbs(False) - self.stdiv(False) - - self.power.tfpwr(output=False) - self.power.component_thermal_powers() - self.power.calculate_cryo_loads() - self.buildings.run(output=False) - self.vacuum.run(output=False) - self.power.acpow(output=False) - self.power.plant_electric_production() - # TODO: should availability.run be called - # rather than availability.avail? - self.availability.avail(output=False) - self.costs.run() - - if 91 in numerics.icc: - # This call is comparably time consuming.. - # If the respective constraint equation is not called, do not set the values - ( - stellarator_variables.powerht_constraint, - stellarator_variables.powerscaling_constraint, - ) = self.power_at_ignition_point( - stellarator_variables.max_gyrotron_frequency, - stellarator_variables.te0_ecrh_achievable, - ) - - stellarator_variables.first_call = False - - def stnewconfig(self): - """author: J Lion, IPP Greifswald - Routine to initialise the stellarator configuration - - Routine to initialise the stellarator configuration. - This routine is called right before the calculation and could - in principle overwrite variables from the input file. - It overwrites rminor with rmajor and aspect ratio e.g. - """ - - load_stellarator_config( - stellarator_variables.istell, - Path(f"{global_variables.output_prefix}stella_conf.json"), - ) - - # If physics_variables.aspect ratio is not in numerics.ixc set it to default value - # Or when you call it the first time - if 1 not in numerics.ixc: - physics_variables.aspect = stellarator_configuration.stella_config_aspect_ref - - # Set the physics_variables.rminor radius as result here. - physics_variables.rminor = physics_variables.rmajor / physics_variables.aspect - physics_variables.eps = 1.0e0 / physics_variables.aspect - - tfcoil_variables.n_tf_coils = ( - stellarator_configuration.stella_config_coilspermodule - * stellarator_configuration.stella_config_symmetry - ) # This overwrites tfcoil_variables.n_tf_coils in input file. - - # Factors used to scale the reference point. - stellarator_variables.f_r = ( - physics_variables.rmajor / stellarator_configuration.stella_config_rmajor_ref - ) # Size scaling factor with respect to the reference calculation - stellarator_variables.f_a = ( - physics_variables.rminor / stellarator_configuration.stella_config_rminor_ref - ) # Size scaling factor with respect to the reference calculation - - stellarator_variables.f_aspect = ( - physics_variables.aspect / stellarator_configuration.stella_config_aspect_ref - ) - stellarator_variables.f_n = tfcoil_variables.n_tf_coils / ( - stellarator_configuration.stella_config_coilspermodule - * stellarator_configuration.stella_config_symmetry - ) # Coil number factor - stellarator_variables.f_b = ( - physics_variables.b_plasma_toroidal_on_axis - / stellarator_configuration.stella_config_bt_ref - ) # B-field scaling factor - - def stgeom(self): - """ - author: J Lion, IPP Greifswald - Routine to calculate the plasma volume and surface area for - a stellarator using precalculated effective values - - This routine calculates the plasma volume and surface area for - a stellarator configuration. - It is simple scaling based on a Fourier representation based on - that described in Geiger documentation. - - J. Geiger, IPP Greifswald internal document: 'Darstellung von - ineinandergeschachtelten toroidal geschlossenen Flaechen mit - Fourierkoeffizienten' ('Representation of nested, closed - surfaces with Fourier coefficients') - """ - physics_variables.vol_plasma = ( - stellarator_variables.f_r - * stellarator_variables.f_a**2 - * stellarator_configuration.stella_config_vol_plasma - ) - - # Plasma surface scaled from effective parameter: - physics_variables.a_plasma_surface = ( - stellarator_variables.f_r - * stellarator_variables.f_a - * stellarator_configuration.stella_config_plasma_surface - ) - - # Plasma cross section area. Approximated - physics_variables.a_plasma_poloidal = ( - np.pi * physics_variables.rminor * physics_variables.rminor - ) # average, could be calculated for every toroidal angle if desired - - # physics_variables.a_plasma_surface_outboard is retained only for obsolescent fispact calculation... - - # Cross-sectional area, averaged over toroidal angle - physics_variables.a_plasma_surface_outboard = ( - 0.5e0 * physics_variables.a_plasma_surface - ) # Used only in the divertor model; approximate as for tokamaks - - def stopt(self, output: bool): - """Routine to reiterate the physics loop - author: J Lion, IPP Greifswald - None - This routine reiterates some physics modules. - """ - - physics_variables.nd_plasma_electrons_max = self.stdlim( - physics_variables.b_plasma_toroidal_on_axis, - physics_variables.p_plasma_loss_mw, - physics_variables.rmajor, - physics_variables.rminor, - ) - - # Calculates the ECRH parameters - - ne0_max_ECRH, bt_ecrh = self.stdlim_ecrh( - stellarator_variables.max_gyrotron_frequency, - physics_variables.b_plasma_toroidal_on_axis, - ) - - ne0_max_ECRH = min(physics_variables.nd_plasma_electron_on_axis, ne0_max_ECRH) - bt_ecrh = min(physics_variables.b_plasma_toroidal_on_axis, bt_ecrh) - - if output: - self.stopt_output( - stellarator_variables.max_gyrotron_frequency, - physics_variables.b_plasma_toroidal_on_axis, - bt_ecrh, - ne0_max_ECRH, - stellarator_variables.te0_ecrh_achievable, - ) - - def stbild(self, output: bool): - """ - Routine to determine the build of a stellarator machine - author: P J Knight, CCFE, Culham Science Centre - author: F Warmer, IPP Greifswald - outfile : input integer : output file unit - iprint : input integer : switch for writing to output file (1=yes) - This routine determines the build of the stellarator machine. - The values calculated are based on the mean minor radius, etc., - as the actual radial and vertical build thicknesses vary with - toroidal angle. - """ - if fwbs_variables.blktmodel > 0: - build_variables.dr_blkt_inboard = ( - build_variables.blbuith - + build_variables.blbmith - + build_variables.blbpith - ) - build_variables.dr_blkt_outboard = ( - build_variables.blbuoth - + build_variables.blbmoth - + build_variables.blbpoth - ) - build_variables.dz_shld_upper = 0.5e0 * ( - build_variables.dr_shld_inboard + build_variables.dr_shld_outboard - ) - - # Top/bottom blanket thickness - - build_variables.dz_blkt_upper = 0.5e0 * ( - build_variables.dr_blkt_inboard + build_variables.dr_blkt_outboard - ) - - # First Wall - build_variables.dr_fw_inboard = ( - 2.0e0 * fwbs_variables.radius_fw_channel + 2.0e0 * fwbs_variables.dr_fw_wall - ) - build_variables.dr_fw_outboard = build_variables.dr_fw_inboard - - build_variables.dr_bore = physics_variables.rmajor - ( - build_variables.dr_cs - + build_variables.dr_cs_tf_gap - + build_variables.dr_tf_inboard - + build_variables.dr_shld_vv_gap_inboard - + build_variables.dr_vv_inboard - + build_variables.dr_shld_inboard - + build_variables.dr_blkt_inboard - + build_variables.dr_fw_inboard - + build_variables.dr_fw_plasma_gap_inboard - + physics_variables.rminor - ) - - # Radial build to centre of plasma (should be equal to physics_variables.rmajor) - build_variables.rbld = ( - build_variables.dr_bore - + build_variables.dr_cs - + build_variables.dr_cs_tf_gap - + build_variables.dr_tf_inboard - + build_variables.dr_shld_vv_gap_inboard - + build_variables.dr_vv_inboard - + build_variables.dr_shld_inboard - + build_variables.dr_blkt_inboard - + build_variables.dr_fw_inboard - + build_variables.dr_fw_plasma_gap_inboard - + physics_variables.rminor - ) - - # Bc stellarators cannot scale physics_variables.rminor reasonably well an additional constraint equation is required, - # that ensures that there is enough space between coils and plasma. - build_variables.required_radial_space = ( - build_variables.dr_tf_inboard / 2.0e0 - + build_variables.dr_shld_vv_gap_inboard - + build_variables.dr_vv_inboard - + build_variables.dr_shld_inboard - + build_variables.dr_blkt_inboard - + build_variables.dr_fw_inboard - + build_variables.dr_fw_plasma_gap_inboard - ) - - # derivative_min_LCFS_coils_dist for how strong the stellarator shape changes wrt to aspect ratio - build_variables.available_radial_space = stellarator_variables.f_r * ( - stellarator_configuration.stella_config_derivative_min_lcfs_coils_dist - * stellarator_configuration.stella_config_rminor_ref - * (1 / stellarator_variables.f_aspect - 1) - + stellarator_configuration.stella_config_min_plasma_coil_distance - ) - - # Radius to inner edge of inboard shield - build_variables.r_shld_inboard_inner = ( - physics_variables.rmajor - - physics_variables.rminor - - build_variables.dr_fw_plasma_gap_inboard - - build_variables.dr_fw_inboard - - build_variables.dr_blkt_inboard - - build_variables.dr_shld_inboard - ) - - # Radius to outer edge of outboard shield - build_variables.r_shld_outboard_outer = ( - physics_variables.rmajor - + physics_variables.rminor - + build_variables.dr_fw_plasma_gap_outboard - + build_variables.dr_fw_outboard - + build_variables.dr_blkt_outboard - + build_variables.dr_shld_outboard - ) - - # Thickness of outboard TF coil legs - build_variables.dr_tf_outboard = build_variables.dr_tf_inboard - - # Radius to centre of outboard TF coil legs - - build_variables.dr_shld_vv_gap_outboard = build_variables.gapomin - build_variables.r_tf_outboard_mid = ( - build_variables.r_shld_outboard_outer - + build_variables.dr_vv_outboard - + build_variables.dr_shld_vv_gap_outboard - + 0.5e0 * build_variables.dr_tf_outboard - ) - - # Height to inside edge of TF coil - # Roughly equal to average of (inboard build from TF coil to plasma - # centre) and (outboard build from plasma centre to TF coil) - - build_variables.z_tf_inside_half = 0.5e0 * ( - ( - build_variables.dr_shld_vv_gap_inboard - + build_variables.dr_vv_inboard - + build_variables.dr_shld_inboard - + build_variables.dr_blkt_inboard - + build_variables.dr_fw_inboard - + build_variables.dr_fw_plasma_gap_inboard - + physics_variables.rminor - ) - + ( - physics_variables.rminor - + build_variables.dr_fw_plasma_gap_outboard - + build_variables.dr_fw_outboard - + build_variables.dr_blkt_outboard - + build_variables.dr_shld_outboard - + build_variables.dr_vv_outboard - + build_variables.dr_shld_vv_gap_outboard - ) - ) - - # Outer divertor strike point radius, set equal to major radius - - build_variables.rspo = physics_variables.rmajor - - # First wall area: scales with minor radius - - # Average minor radius of the first wall - awall = physics_variables.rminor + 0.5e0 * ( - build_variables.dr_fw_plasma_gap_inboard - + build_variables.dr_fw_plasma_gap_outboard - ) - build_variables.a_fw_total = ( - physics_variables.a_plasma_surface * awall / physics_variables.rminor - ) - - if heat_transport_variables.ipowerflow == 0: - build_variables.a_fw_total = ( - 1.0e0 - fwbs_variables.fhole - ) * build_variables.a_fw_total - else: - build_variables.a_fw_total = ( - 1.0e0 - - fwbs_variables.fhole - - fwbs_variables.f_ster_div_single - - fwbs_variables.f_a_fw_outboard_hcd - ) * build_variables.a_fw_total - - if output: - # Print out device build - - po.oheadr(self.outfile, "Radial Build") - - po.ovarre( - self.outfile, - "Avail. Space (m)", - "(available_radial_space)", - build_variables.available_radial_space, - ) - po.ovarre( - self.outfile, - "Req. Space (m)", - "(required_radial_space)", - build_variables.required_radial_space, - ) - - # po.write(self.outfile,10) - # 10 format(t43,'Thickness (m)',t60,'Radius (m)') - - radius = 0.0e0 - po.obuild(self.outfile, "Device centreline", 0.0e0, radius) - - drbild = ( - build_variables.dr_bore - + build_variables.dr_cs - + build_variables.dr_cs_tf_gap - ) - radius = radius + drbild - po.obuild(self.outfile, "Machine dr_bore", drbild, radius, "(dr_bore)") - po.ovarre( - self.outfile, "Machine build_variables.dr_bore (m)", "(dr_bore)", drbild - ) - - radius = radius + build_variables.dr_tf_inboard - po.obuild( - self.outfile, - "Coil inboard leg", - build_variables.dr_tf_inboard, - radius, - "(dr_tf_inboard)", - ) - po.ovarre( - self.outfile, - "Coil inboard leg (m)", - "(deltf)", - build_variables.dr_tf_inboard, - ) - - radius = radius + build_variables.dr_shld_vv_gap_inboard - po.obuild( - self.outfile, - "Gap", - build_variables.dr_shld_vv_gap_inboard, - radius, - "(dr_shld_vv_gap_inboard)", - ) - po.ovarre( - self.outfile, - "Gap (m)", - "(dr_shld_vv_gap_inboard)", - build_variables.dr_shld_vv_gap_inboard, - ) - - radius = radius + build_variables.dr_vv_inboard - po.obuild( - self.outfile, - "Vacuum vessel", - build_variables.dr_vv_inboard, - radius, - "(dr_vv_inboard)", - ) - po.ovarre( - self.outfile, - "Vacuum vessel radial thickness (m)", - "(dr_vv_inboard)", - build_variables.dr_vv_inboard, - ) - - radius = radius + build_variables.dr_shld_inboard - po.obuild( - self.outfile, - "Inboard shield", - build_variables.dr_shld_inboard, - radius, - "(dr_shld_inboard)", - ) - po.ovarre( - self.outfile, - "Inner radiation shield radial thickness (m)", - "(dr_shld_inboard)", - build_variables.dr_shld_inboard, - ) - - radius = radius + build_variables.dr_blkt_inboard - po.obuild( - self.outfile, - "Inboard blanket", - build_variables.dr_blkt_inboard, - radius, - "(dr_blkt_inboard)", - ) - po.ovarre( - self.outfile, - "Inboard blanket radial thickness (m)", - "(dr_blkt_inboard)", - build_variables.dr_blkt_inboard, - ) - - radius = radius + build_variables.dr_fw_inboard - po.obuild( - self.outfile, - "Inboard first wall", - build_variables.dr_fw_inboard, - radius, - "(dr_fw_inboard)", - ) - po.ovarre( - self.outfile, - "Inboard first wall radial thickness (m)", - "(dr_fw_inboard)", - build_variables.dr_fw_inboard, - ) - - radius = radius + build_variables.dr_fw_plasma_gap_inboard - po.obuild( - self.outfile, - "Inboard scrape-off", - build_variables.dr_fw_plasma_gap_inboard, - radius, - "(dr_fw_plasma_gap_inboard)", - ) - po.ovarre( - self.outfile, - "Inboard scrape-off radial thickness (m)", - "(dr_fw_plasma_gap_inboard)", - build_variables.dr_fw_plasma_gap_inboard, - ) - - radius = radius + physics_variables.rminor - po.obuild( - self.outfile, - "Plasma geometric centre", - physics_variables.rminor, - radius, - "(rminor)", - ) - - radius = radius + physics_variables.rminor - po.obuild( - self.outfile, - "Plasma outboard edge", - physics_variables.rminor, - radius, - "(rminor)", - ) - - radius = radius + build_variables.dr_fw_plasma_gap_outboard - po.obuild( - self.outfile, - "Outboard scrape-off", - build_variables.dr_fw_plasma_gap_outboard, - radius, - "(dr_fw_plasma_gap_outboard)", - ) - po.ovarre( - self.outfile, - "Outboard scrape-off radial thickness (m)", - "(dr_fw_plasma_gap_outboard)", - build_variables.dr_fw_plasma_gap_outboard, - ) - - radius = radius + build_variables.dr_fw_outboard - po.obuild( - self.outfile, - "Outboard first wall", - build_variables.dr_fw_outboard, - radius, - "(dr_fw_outboard)", - ) - po.ovarre( - self.outfile, - "Outboard first wall radial thickness (m)", - "(dr_fw_outboard)", - build_variables.dr_fw_outboard, - ) - - radius = radius + build_variables.dr_blkt_outboard - po.obuild( - self.outfile, - "Outboard blanket", - build_variables.dr_blkt_outboard, - radius, - "(dr_blkt_outboard)", - ) - po.ovarre( - self.outfile, - "Outboard blanket radial thickness (m)", - "(dr_blkt_outboard)", - build_variables.dr_blkt_outboard, - ) - - radius = radius + build_variables.dr_shld_outboard - po.obuild( - self.outfile, - "Outboard shield", - build_variables.dr_shld_outboard, - radius, - "(dr_shld_outboard)", - ) - po.ovarre( - self.outfile, - "Outer radiation shield radial thickness (m)", - "(dr_shld_outboard)", - build_variables.dr_shld_outboard, - ) - - radius = radius + build_variables.dr_vv_outboard - po.obuild( - self.outfile, - "Vacuum vessel", - build_variables.dr_vv_outboard, - radius, - "(dr_vv_outboard)", - ) - - radius = radius + build_variables.dr_shld_vv_gap_outboard - po.obuild( - self.outfile, - "Gap", - build_variables.dr_shld_vv_gap_outboard, - radius, - "(dr_shld_vv_gap_outboard)", - ) - po.ovarre( - self.outfile, - "Gap (m)", - "(dr_shld_vv_gap_outboard)", - build_variables.dr_shld_vv_gap_outboard, - ) - - radius = radius + build_variables.dr_tf_outboard - po.obuild( - self.outfile, - "Coil outboard leg", - build_variables.dr_tf_outboard, - radius, - "(dr_tf_outboard)", - ) - po.ovarre( - self.outfile, - "Coil outboard leg radial thickness (m)", - "(dr_tf_outboard)", - build_variables.dr_tf_outboard, - ) - - def ststrc(self, output): - """ - Routine to calculate the structural masses for a stellarator - author: P J Knight, CCFE, Culham Science Centre - outfile : input integer : output file unit - iprint : input integer : switch for writing to output file (1=yes) - This routine calculates the structural masses for a stellarator. - This is the stellarator version of routine - STRUCT. In practice, many of the masses - are simply set to zero to avoid double-counting of structural - components that are specified differently for tokamaks. - """ - structure_variables.fncmass = 0.0e0 - - # Reactor core gravity support mass - structure_variables.gsmass = 0.0e0 # ? Not sure about this. - - # This is the previous scaling law for intercoil structure - # We keep is here as a reference to the new model, which - # we do not really trust yet. - # Mass of support structure (includes casing) (tonnes) - # Scaling for required structure mass (Steel) from: - # F.C. Moon, J. Appl. Phys. 53(12) (1982) 9112 - # - # Values based on regression analysis by Greifswald, March 2014 - m_struc = ( - 1.3483e0 - * (1000.0e0 * tfcoil_variables.e_tf_magnetic_stored_total_gj) ** 0.7821e0 - ) - msupstr = 1000.0e0 * m_struc # kg - - ################################################################ - # Intercoil support structure calculation: - # Calculate the intercoil bolted plates structure from the coil surface - # which needs to be precalculated (or calculated in PROCESS but this not done here) - # The coil width is subtracted from that: - # total_coil_width = b + 2* d_ic + 2* case_thickness_constant - # total_coil_thickness = h + 2* d_ic + 2* case_thickness_constant - - # The following line is correct AS LONG AS we do not scale the coil sizes - intercoil_surface = ( - stellarator_configuration.stella_config_coilsurface - * stellarator_variables.f_r**2 - - tfcoil_variables.dx_tf_inboard_out_toroidal - * stellarator_configuration.stella_config_coillength - * stellarator_variables.f_r - * stellarator_variables.f_n - ) - - # This 0.18 m is an effective thickness which is scaled with empirial 1.5 law. 5.6 T is reference point of Helias - # The thickness 0.18m was obtained as a measured value from Schauer, F. and Bykov, V. design of Helias 5-B. (Nucl Fus. 2013) - structure_variables.aintmass = ( - 0.18e0 - * stellarator_variables.f_b**2 - * intercoil_surface - * fwbs_variables.den_steel - ) - - structure_variables.clgsmass = ( - 0.2e0 * structure_variables.aintmass - ) # Very simple approximation for the gravity support. - # This fits for the Helias 5b reactor design point ( F. and Bykov, V. design of Helias 5-B. (nucl Fus. 2013)). - - # Total mass of cooled components - structure_variables.coldmass = ( - tfcoil_variables.m_tf_coils_total - + structure_variables.aintmass - + fwbs_variables.dewmkg - ) - - # Output section - - if output: - po.oheadr(self.outfile, "Support Structure") - po.ovarre( - self.outfile, - "Intercoil support structure mass (from intercoil calculation) (kg)", - "(aintmass)", - structure_variables.aintmass, - ) - po.ovarre( - self.outfile, - "Intercoil support structure mass (scaling, for comparison) (kg)", - "(empiricalmass)", - msupstr, - ) - po.ovarre( - self.outfile, - "Gravity support structure mass (kg)", - "(clgsmass)", - structure_variables.clgsmass, - ) - po.ovarre( - self.outfile, - "Mass of cooled components (kg)", - "(coldmass)", - structure_variables.coldmass, - ) - - def stdiv(self, output: bool): - """Routine to call the stellarator divertor model - author: P J Knight, CCFE, Culham Science Centre - author: F Warmer, IPP Greifswald - outfile : input integer : output file unit - iprint : input integer : switch for writing to output file (1=yes) - This routine calls the divertor model for a stellarator, - developed by Felix Warmer. - Stellarator Divertor Model for the Systems - Code PROCESS, F. Warmer, 21/06/2013 - """ - Theta = stellarator_variables.flpitch # ~bmn [rad] field line pitch - r = physics_variables.rmajor - p_div = physics_variables.p_plasma_separatrix_mw - alpha = divertor_variables.anginc - xi_p = divertor_variables.xpertin - T_scrape = divertor_variables.tdiv - - # Scrape-off temperature in Joules - - e = T_scrape * constants.ELECTRON_CHARGE - - # Sound speed of particles (m/s) - - c_s = np.sqrt(e / (physics_variables.m_fuel_amu * constants.UMASS)) - - # Island size (m) - - w_r = 4.0e0 * np.sqrt( - stellarator_variables.bmn - * r - / (stellarator_variables.shear * stellarator_variables.n_res) - ) - - # Perpendicular (to plate) distance from X-point to divertor plate (m) - - Delta = stellarator_variables.f_w * w_r - - # Length 'along' plasma (m) - - l_p = 2 * np.pi * r * (stellarator_variables.m_res) / stellarator_variables.n_res - - # Connection length from X-point to divertor plate (m) - - l_x_t = Delta / Theta - - # Power decay length (m) - - l_q = np.sqrt(xi_p * (l_x_t / c_s)) - - # Channel broadening length (m) - - l_b = np.sqrt(xi_p * l_p / (c_s)) - - # Channel broadening factor - - f_x = 1.0e0 + (l_b / (l_p * Theta)) - - # Length of a single divertor plate (m) - - l_d = f_x * l_p * (Theta / alpha) - - # Total length of divertor plates (m) - - l_t = 2.0e0 * stellarator_variables.n_res * l_d - - # Wetted area (m2) - - a_eff = l_t * l_q - - # Divertor plate width (m): assume total area is wetted area/stellarator_variables.fdivwet - - darea = a_eff / stellarator_variables.fdivwet - l_w = darea / l_t - - # Divertor heat load (MW/m2) - - q_div = stellarator_variables.f_asym * (p_div / a_eff) - - # Transfer to global variables - - divertor_variables.pflux_div_heat_load_mw = q_div - divertor_variables.a_div_surface_total = darea - - fwbs_variables.f_ster_div_single = darea / build_variables.a_fw_total - - if output: - po.oheadr(self.outfile, "Divertor") - - po.ovarre( - self.outfile, - "Power to divertor (MW)", - "(p_plasma_separatrix_mw.)", - physics_variables.p_plasma_separatrix_mw, - ) - po.ovarre( - self.outfile, - "Angle of incidence (deg)", - "(anginc)", - divertor_variables.anginc * 180.0e0 / np.pi, - ) - po.ovarre( - self.outfile, - "Perp. heat transport coefficient (m2/s)", - "(xpertin)", - divertor_variables.xpertin, - ) - po.ovarre( - self.outfile, - "Divertor plasma temperature (eV)", - "(tdiv)", - divertor_variables.tdiv, - ) - po.ovarre( - self.outfile, - "Radiated power fraction in SOL", - "(f_rad)", - stellarator_variables.f_rad, - ) - po.ovarre( - self.outfile, - "Heat load peaking factor", - "(f_asym)", - stellarator_variables.f_asym, - ) - po.ovarin( - self.outfile, - "Poloidal resonance number", - "(m_res)", - stellarator_variables.m_res, - ) - po.ovarin( - self.outfile, - "Toroidal resonance number", - "(n_res)", - stellarator_variables.n_res, - ) - po.ovarre( - self.outfile, - "Relative radial field perturbation", - "(bmn)", - stellarator_variables.bmn, - ) - po.ovarre( - self.outfile, - "Field line pitch (rad)", - "(flpitch)", - stellarator_variables.flpitch, - ) - po.ovarre( - self.outfile, - "Island size fraction factor", - "(f_w)", - stellarator_variables.f_w, - ) - po.ovarre( - self.outfile, - "Magnetic stellarator_variables.shear (/m)", - "(shear)", - stellarator_variables.shear, - ) - po.ovarre(self.outfile, "Divertor wetted area (m2)", "(A_eff)", a_eff) - po.ovarre( - self.outfile, - "Wetted area fraction of total plate area", - "(fdivwet)", - stellarator_variables.fdivwet, - ) - po.ovarre(self.outfile, "Divertor plate length (m)", "(L_d)", l_d) - po.ovarre(self.outfile, "Divertor plate width (m)", "(L_w)", l_w) - po.ovarre(self.outfile, "Flux channel broadening factor", "(F_x)", f_x) - po.ovarre(self.outfile, "Power decay width (cm)", "(100*l_q)", 100.0e0 * l_q) - po.ovarre(self.outfile, "Island width (m)", "(w_r)", w_r) - po.ovarre( - self.outfile, - "Perp. distance from X-point to plate (m)", - "(Delta)", - Delta, - ) - po.ovarre( - self.outfile, - "Peak heat load (MW/m2)", - "(pflux_div_heat_load_mw)", - divertor_variables.pflux_div_heat_load_mw, - ) - - def blanket_neutronics(self): - # heating of the blanket - if fwbs_variables.breedmat == 1: - fwbs_variables.breeder = "Orthosilicate" - fwbs_variables.densbreed = 1.50e3 - elif fwbs_variables.breedmat == 2: - fwbs_variables.breeder = "Metatitanate" - fwbs_variables.densbreed = 1.78e3 - else: - fwbs_variables.breeder = ( - "Zirconate" # (In reality, rarely used - activation problems) - ) - fwbs_variables.densbreed = 2.12e3 - - fwbs_variables.m_blkt_total = ( - fwbs_variables.vol_blkt_total * fwbs_variables.densbreed - ) - self.hcpb.nuclear_heating_blanket() - - # Heating of the magnets - self.hcpb.nuclear_heating_magnets(False) - - # Rough estimate of TF coil volume used, assuming 25% of the total - # TF coil perimeter is inboard, 75% outboard - tf_volume = ( - 0.25 * tfcoil_variables.len_tf_coil * tfcoil_variables.a_tf_inboard_total - + 0.75 - * tfcoil_variables.len_tf_coil - * tfcoil_variables.a_tf_leg_outboard - * tfcoil_variables.n_tf_coils - ) - - fwbs_variables.ptfnucpm3 = fwbs_variables.p_tf_nuclear_heat_mw / tf_volume - - # heating of the shield - self.hcpb.nuclear_heating_shield() - - # Energy multiplication factor - fwbs_variables.f_p_blkt_multiplication = 1.269 - - # Use older model to calculate neutron fluence since it - # is not calculated in the CCFE blanket model - ( - _, - _, - _, - fwbs_variables.nflutf, - _, - _, - _, - _, - _, - _, - ) = self.sctfcoil_nuclear_heating_iter90() - - # blktlife calculation left entierly to availability - # Cannot find calculation for vvhemax in CCFE blanket - - def stfwbs(self, output: bool): - """Routine to calculate first wall, blanket and shield properties - for a stellarator - author: P J Knight, CCFE, Culham Science Centre - author: F Warmer, IPP Greifswald - outfile : input integer : Fortran output unit identifier - iprint : input integer : Switch to write output to file (1=yes) - This routine calculates a stellarator's first wall, blanket and - shield properties. - It calculates the nuclear heating in the blanket / shield, and - estimates the volume and masses of the first wall, - blanket, shield and vacuum vessel. -

The arrays coef(i,j) and decay(i,j) - are used for exponential decay approximations of the - (superconducting) TF coil nuclear parameters. -

- Note: Costing and mass calculations elsewhere assume - stainless steel only. -

The method is the same as for tokamaks (as performed via - fwbs), except for the volume calculations, - which scale the surface area of the components from that - of the plasma. - """ - fwbs_variables.life_fw_fpy = min( - cost_variables.abktflnc / physics_variables.pflux_fw_neutron_mw, - cost_variables.life_plant, - ) - - # First wall inboard, outboard areas (assume 50% of total each) - build_variables.a_fw_inboard = 0.5e0 * build_variables.a_fw_total - build_variables.a_fw_outboard = 0.5e0 * build_variables.a_fw_total - - # Blanket volume; assume that its surface area is scaled directly from the - # plasma surface area. - # Uses fwbs_variables.fhole etc. to take account of gaps due to ports etc. - - r1 = physics_variables.rminor + 0.5e0 * ( - build_variables.dr_fw_plasma_gap_inboard - + build_variables.dr_fw_inboard - + build_variables.dr_fw_plasma_gap_outboard - + build_variables.dr_fw_outboard - ) - if heat_transport_variables.ipowerflow == 0: - build_variables.a_blkt_total_surface = ( - physics_variables.a_plasma_surface - * r1 - / physics_variables.rminor - * (1.0e0 - fwbs_variables.fhole) - ) - else: - build_variables.a_blkt_total_surface = ( - physics_variables.a_plasma_surface - * r1 - / physics_variables.rminor - * ( - 1.0e0 - - fwbs_variables.fhole - - fwbs_variables.f_ster_div_single - - fwbs_variables.f_a_fw_outboard_hcd - ) - ) - - build_variables.a_blkt_inboard_surface = ( - 0.5e0 * build_variables.a_blkt_total_surface - ) - build_variables.a_blkt_outboard_surface = ( - 0.5e0 * build_variables.a_blkt_total_surface - ) - - fwbs_variables.vol_blkt_inboard = ( - build_variables.a_blkt_inboard_surface * build_variables.dr_blkt_inboard - ) - fwbs_variables.vol_blkt_outboard = ( - build_variables.a_blkt_outboard_surface * build_variables.dr_blkt_outboard - ) - fwbs_variables.vol_blkt_total = ( - fwbs_variables.vol_blkt_inboard + fwbs_variables.vol_blkt_outboard - ) - - # Shield volume - # Uses fvolsi, fwbs_variables.fvolso as area coverage factors - - r1 = r1 + 0.5e0 * ( - build_variables.dr_blkt_inboard + build_variables.dr_blkt_outboard - ) - build_variables.a_shld_total_surface = ( - physics_variables.a_plasma_surface * r1 / physics_variables.rminor - ) - build_variables.a_shld_inboard_surface = ( - 0.5e0 * build_variables.a_shld_total_surface * fwbs_variables.fvolsi - ) - build_variables.a_shld_outboard_surface = ( - 0.5e0 * build_variables.a_shld_total_surface * fwbs_variables.fvolso - ) - - vol_shld_inboard = ( - build_variables.a_shld_inboard_surface * build_variables.dr_shld_inboard - ) - vol_shld_outboard = ( - build_variables.a_shld_outboard_surface * build_variables.dr_shld_outboard - ) - fwbs_variables.vol_shld_total = vol_shld_inboard + vol_shld_outboard - - # Neutron power lost through holes in first wall (eventually absorbed by - # shield) - - fwbs_variables.pnucloss = ( - physics_variables.p_neutron_total_mw * fwbs_variables.fhole - ) - - # The peaking factor, obtained as precalculated parameter - fwbs_variables.wallpf = ( - stellarator_configuration.stella_config_neutron_peakfactor - ) - - # Blanket neutronics calculations - if fwbs_variables.blktmodel == 1: - self.blanket_neutronics() - - if heat_transport_variables.ipowerflow == 1: - fwbs_variables.p_div_nuclear_heat_total_mw = ( - physics_variables.p_neutron_total_mw - * fwbs_variables.f_ster_div_single - ) - fwbs_variables.p_fw_hcd_nuclear_heat_mw = ( - physics_variables.p_neutron_total_mw - * fwbs_variables.f_a_fw_outboard_hcd - ) - fwbs_variables.p_fw_nuclear_heat_total_mw = ( - physics_variables.p_neutron_total_mw - - fwbs_variables.p_div_nuclear_heat_total_mw - - fwbs_variables.pnucloss - - fwbs_variables.p_fw_hcd_nuclear_heat_mw - ) - - fwbs_variables.pradloss = ( - physics_variables.p_plasma_rad_mw * fwbs_variables.fhole - ) - fwbs_variables.p_div_rad_total_mw = ( - physics_variables.p_plasma_rad_mw * fwbs_variables.f_ster_div_single - ) - fwbs_variables.p_fw_hcd_rad_total_mw = ( - physics_variables.p_plasma_rad_mw - * fwbs_variables.f_a_fw_outboard_hcd - ) - fwbs_variables.p_fw_rad_total_mw = ( - physics_variables.p_plasma_rad_mw - - fwbs_variables.p_div_rad_total_mw - - fwbs_variables.pradloss - - fwbs_variables.p_fw_hcd_rad_total_mw - ) - - heat_transport_variables.p_fw_coolant_pump_mw = ( - heat_transport_variables.f_p_fw_coolant_pump_total_heat - * ( - fwbs_variables.p_fw_nuclear_heat_total_mw - + fwbs_variables.p_fw_rad_total_mw - + current_drive_variables.p_beam_orbit_loss_mw - ) - ) - heat_transport_variables.p_blkt_coolant_pump_mw = ( - heat_transport_variables.f_p_blkt_coolant_pump_total_heat - * fwbs_variables.p_blkt_nuclear_heat_total_mw - ) - heat_transport_variables.p_shld_coolant_pump_mw = ( - heat_transport_variables.f_p_shld_coolant_pump_total_heat - * fwbs_variables.p_shld_nuclear_heat_mw - ) - heat_transport_variables.p_div_coolant_pump_mw = ( - heat_transport_variables.f_p_div_coolant_pump_total_heat - * ( - physics_variables.p_plasma_separatrix_mw - + fwbs_variables.p_div_nuclear_heat_total_mw - + fwbs_variables.p_div_rad_total_mw - ) - ) - - # Void fraction in first wall / breeding zone, - # for use in fwbs_variables.m_fw_total and coolvol calculation below - - f_a_fw_coolant_inboard = ( - 1.0e0 - - fwbs_variables.fblbe - - fwbs_variables.fblbreed - - fwbs_variables.fblss - ) - f_a_fw_coolant_outboard = f_a_fw_coolant_inboard - - else: - fwbs_variables.pnuc_cp = 0.0e0 - - if heat_transport_variables.ipowerflow == 0: - # Energy-multiplied neutron power - - pneut2 = ( - physics_variables.p_neutron_total_mw - - fwbs_variables.pnucloss - - fwbs_variables.pnuc_cp - ) * fwbs_variables.f_p_blkt_multiplication - - fwbs_variables.p_blkt_multiplication_mw = pneut2 - ( - physics_variables.p_neutron_total_mw - - fwbs_variables.pnucloss - - fwbs_variables.pnuc_cp - ) - - # Nuclear heating in the blanket - - decaybl = 0.075e0 / ( - 1.0e0 - - fwbs_variables.f_a_blkt_cooling_channels - - fwbs_variables.fblli2o - - fwbs_variables.fblbe - ) - - fwbs_variables.p_blkt_nuclear_heat_total_mw = pneut2 * ( - 1.0e0 - np.exp(-build_variables.dr_blkt_outboard / decaybl) - ) - - # Nuclear heating in the shield - fwbs_variables.p_shld_nuclear_heat_mw = ( - pneut2 - fwbs_variables.p_blkt_nuclear_heat_total_mw - ) - - # Superconducting coil shielding calculations - ( - coilhtmx, - dpacop, - htheci, - fwbs_variables.nflutf, - pheci, - pheco, - ptfiwp, - ptfowp, - raddose, - fwbs_variables.p_tf_nuclear_heat_mw, - ) = self.sctfcoil_nuclear_heating_iter90() - - else: # heat_transport_variables.ipowerflow == 1 - # Neutron power incident on divertor (MW) - - fwbs_variables.p_div_nuclear_heat_total_mw = ( - physics_variables.p_neutron_total_mw - * fwbs_variables.f_ster_div_single - ) - - # Neutron power incident on HCD apparatus (MW) - - fwbs_variables.p_fw_hcd_nuclear_heat_mw = ( - physics_variables.p_neutron_total_mw - * fwbs_variables.f_a_fw_outboard_hcd - ) - - # Neutron power deposited in first wall, blanket and shield (MW) - - pnucfwbs = ( - physics_variables.p_neutron_total_mw - - fwbs_variables.p_div_nuclear_heat_total_mw - - fwbs_variables.pnucloss - - fwbs_variables.pnuc_cp - - fwbs_variables.p_fw_hcd_nuclear_heat_mw - ) - - # Split between inboard and outboard by first wall area fractions - - pnucfwbsi = ( - pnucfwbs * build_variables.a_fw_inboard / build_variables.a_fw_total - ) - pnucfwbso = ( - pnucfwbs * build_variables.a_fw_outboard / build_variables.a_fw_total - ) - - # Radiation power incident on divertor (MW) - - fwbs_variables.p_div_rad_total_mw = ( - physics_variables.p_plasma_rad_mw * fwbs_variables.f_ster_div_single - ) - - # Radiation power incident on HCD apparatus (MW) - - fwbs_variables.p_fw_hcd_rad_total_mw = ( - physics_variables.p_plasma_rad_mw - * fwbs_variables.f_a_fw_outboard_hcd - ) - - # Radiation power lost through holes (eventually hits shield) (MW) - - fwbs_variables.pradloss = ( - physics_variables.p_plasma_rad_mw * fwbs_variables.fhole - ) - - # Radiation power incident on first wall (MW) - - fwbs_variables.p_fw_rad_total_mw = ( - physics_variables.p_plasma_rad_mw - - fwbs_variables.p_div_rad_total_mw - - fwbs_variables.pradloss - - fwbs_variables.p_fw_hcd_rad_total_mw - ) - - # Calculate the power deposited in the first wall, blanket and shield, - # and the required coolant pumping power - - # If we have chosen pressurised water as the coolant, set the - # coolant outlet temperature as 20 deg C below the boiling point - - if fwbs_variables.i_blkt_coolant_type == 2: - if fwbs_variables.irefprop: - fwbs_variables.temp_blkt_coolant_out = ( - FluidProperties.of( - "Water", - pressure=fwbs_variables.coolp, - vapor_quality=0, - ) - - 20 - ) - else: - fwbs_variables.temp_blkt_coolant_out = ( - 273.15 - + 168.396 - + 0.314653 / fwbs_variables.coolp - + -0.000728 / fwbs_variables.coolp**2 - + 31.588979 * np.log(fwbs_variables.coolp) - + 11.473141 * fwbs_variables.coolp - + -0.575335 * fwbs_variables.coolp**2 - + 0.013165 * fwbs_variables.coolp**3 - ) - 20 - - bfwi = 0.5e0 * build_variables.dr_fw_inboard - bfwo = 0.5e0 * build_variables.dr_fw_outboard - - f_a_fw_coolant_inboard = ( - fwbs_variables.radius_fw_channel - * fwbs_variables.radius_fw_channel - / (bfwi * bfwi) - ) # inboard FW coolant void fraction - f_a_fw_coolant_outboard = ( - fwbs_variables.radius_fw_channel - * fwbs_variables.radius_fw_channel - / (bfwo * bfwo) - ) # outboard FW coolant void fraction - - # First wall decay length (m) - improved calculation required - - decayfwi = fwbs_variables.declfw - decayfwo = fwbs_variables.declfw - - # Surface heat flux on first wall (MW) (sum = fwbs_variables.p_fw_rad_total_mw) - - psurffwi = ( - fwbs_variables.p_fw_rad_total_mw - * build_variables.a_fw_inboard - / build_variables.a_fw_total - ) - psurffwo = ( - fwbs_variables.p_fw_rad_total_mw - * build_variables.a_fw_outboard - / build_variables.a_fw_total - ) - - # Simple blanket model (fwbs_variables.i_p_coolant_pumping = 0 or 1) is assumed for stellarators - - # The power deposited in the first wall, breeder zone and shield is - # calculated according to their dimensions and materials assuming - # an exponential attenuation of nuclear heating with increasing - # radial distance. The pumping power for the coolant is calculated - # as a fraction of the total thermal power deposited in the - # coolant. - - p_fw_inboard_nuclear_heat_mw = pnucfwbsi * ( - 1.0e0 - np.exp(-2.0e0 * bfwi / decayfwi) - ) - p_fw_outboard_nuclear_heat_mw = pnucfwbso * ( - 1.0e0 - np.exp(-2.0e0 * bfwo / decayfwo) - ) - - # Neutron power reaching blanket and shield (MW) - - pnucbsi = pnucfwbsi - p_fw_inboard_nuclear_heat_mw - pnucbso = pnucfwbso - p_fw_outboard_nuclear_heat_mw - - # Blanket decay length (m) - improved calculation required - - decaybzi = fwbs_variables.declblkt - decaybzo = fwbs_variables.declblkt - - # Neutron power deposited in breeder zone (MW) - - pnucbzi = pnucbsi * ( - 1.0e0 - np.exp(-build_variables.dr_blkt_inboard / decaybzi) - ) - pnucbzo = pnucbso * ( - 1.0e0 - np.exp(-build_variables.dr_blkt_outboard / decaybzo) - ) - - # Calculate coolant pumping powers from input fraction. - # The pumping power is assumed to be a fraction, fpump, of the - # incident thermal power to each component so that - # htpmw_i = fpump_i*C, where C is the non-pumping thermal power - # deposited in the coolant - - # First wall and Blanket pumping power (MW) - - if fwbs_variables.i_p_coolant_pumping == 0: - # Use input - pass - elif fwbs_variables.i_p_coolant_pumping == 1: - heat_transport_variables.p_fw_coolant_pump_mw = ( - heat_transport_variables.f_p_fw_coolant_pump_total_heat - * ( - p_fw_inboard_nuclear_heat_mw - + p_fw_outboard_nuclear_heat_mw - + psurffwi - + psurffwo - + current_drive_variables.p_beam_orbit_loss_mw - ) - ) - heat_transport_variables.p_blkt_coolant_pump_mw = ( - heat_transport_variables.f_p_blkt_coolant_pump_total_heat - * ( - pnucbzi * fwbs_variables.f_p_blkt_multiplication - + pnucbzo * fwbs_variables.f_p_blkt_multiplication - ) - ) - else: - raise ProcessValueError( - "i_p_coolant_pumping = 0 or 1 only for stellarator" - ) - - fwbs_variables.p_blkt_multiplication_mw = ( - heat_transport_variables.f_p_blkt_coolant_pump_total_heat - * (pnucbzi * fwbs_variables.f_p_blkt_multiplication + pnucbzo) - * (fwbs_variables.f_p_blkt_multiplication - 1.0e0) - ) - - # Total nuclear heating of first wall (MW) - - fwbs_variables.p_fw_nuclear_heat_total_mw = ( - p_fw_inboard_nuclear_heat_mw + p_fw_outboard_nuclear_heat_mw - ) - - # Total nuclear heating of blanket (MW) - - fwbs_variables.p_blkt_nuclear_heat_total_mw = ( - pnucbzi + pnucbzo - ) * fwbs_variables.f_p_blkt_multiplication - - fwbs_variables.p_blkt_multiplication_mw = ( - fwbs_variables.p_blkt_multiplication_mw - + (pnucbzi + pnucbzo) - * (fwbs_variables.f_p_blkt_multiplication - 1.0e0) - ) - - # Calculation of shield and divertor powers - # Shield and divertor powers and pumping powers are calculated using the same - # simplified method as the first wall and breeder zone when fwbs_variables.i_p_coolant_pumping = 1. - # i.e. the pumping power is a fraction of the total thermal power deposited in the - # coolant. - - # Neutron power reaching the shield (MW) - # The power lost from the fwbs_variables.fhole area fraction is assumed to be incident upon the shield - - pnucsi = ( - pnucbsi - - pnucbzi - + (fwbs_variables.pnucloss + fwbs_variables.pradloss) - * build_variables.a_fw_inboard - / build_variables.a_fw_total - ) - pnucso = ( - pnucbso - - pnucbzo - + (fwbs_variables.pnucloss + fwbs_variables.pradloss) - * build_variables.a_fw_outboard - / build_variables.a_fw_total - ) - - # Improved calculation of shield power decay lengths required - - decayshldi = fwbs_variables.declshld - decayshldo = fwbs_variables.declshld - - # Neutron power deposited in the shield (MW) - - pnucshldi = pnucsi * ( - 1.0e0 - np.exp(-build_variables.dr_shld_inboard / decayshldi) - ) - pnucshldo = pnucso * ( - 1.0e0 - np.exp(-build_variables.dr_shld_outboard / decayshldo) - ) - - fwbs_variables.p_shld_nuclear_heat_mw = pnucshldi + pnucshldo - - # Calculate coolant pumping powers from input fraction. - # The pumping power is assumed to be a fraction, fpump, of the incident - # thermal power to each component so that, - # htpmw_i = fpump_i*C - # where C is the non-pumping thermal power deposited in the coolant - - if fwbs_variables.i_p_coolant_pumping == 1: - # Shield pumping power (MW) - heat_transport_variables.p_shld_coolant_pump_mw = ( - heat_transport_variables.f_p_shld_coolant_pump_total_heat - * (pnucshldi + pnucshldo) - ) - - # Divertor pumping power (MW) - heat_transport_variables.p_div_coolant_pump_mw = ( - heat_transport_variables.f_p_div_coolant_pump_total_heat - * ( - physics_variables.p_plasma_separatrix_mw - + fwbs_variables.p_div_nuclear_heat_total_mw - + fwbs_variables.p_div_rad_total_mw - ) - ) - - # Remaining neutron power to coils and else:where. This is assumed - # (for superconducting coils at least) to be absorbed by the - # coils, and so contributes to the cryogenic load - - if tfcoil_variables.i_tf_sup == 1: - fwbs_variables.p_tf_nuclear_heat_mw = ( - pnucsi + pnucso - pnucshldi - pnucshldo - ) - else: # resistive coils - fwbs_variables.p_tf_nuclear_heat_mw = 0.0e0 - - # heat_transport_variables.ipowerflow - - # fwbs_variables.blktmodel - - # Divertor mass - # N.B. divertor_variables.a_div_surface_total is calculated in stdiv after this point, so will - # be zero on first lap, hence the initial approximation - - if self.first_call_stfwbs: - divertor_variables.a_div_surface_total = 50.0e0 - self.first_call_stfwbs = False - - divertor_variables.m_div_plate = ( - divertor_variables.a_div_surface_total - * divertor_variables.den_div_structure - * (1.0e0 - divertor_variables.f_vol_div_coolant) - * divertor_variables.dx_div_plate - ) - - # Start adding components of the coolant mass: - # Divertor coolant volume (m3) - - coolvol = ( - divertor_variables.a_div_surface_total - * divertor_variables.f_vol_div_coolant - * divertor_variables.dx_div_plate - ) - - # Blanket mass, excluding coolant - - if fwbs_variables.blktmodel == 0: - if (fwbs_variables.blkttype == 1) or ( - fwbs_variables.blkttype == 2 - ): # liquid breeder (WCLL or HCLL) - fwbs_variables.wtbllipb = ( - fwbs_variables.vol_blkt_total * fwbs_variables.fbllipb * 9400.0e0 - ) - fwbs_variables.m_blkt_lithium = ( - fwbs_variables.vol_blkt_total * fwbs_variables.fblli * 534.0e0 - ) - fwbs_variables.m_blkt_total = ( - fwbs_variables.wtbllipb + fwbs_variables.m_blkt_lithium - ) - else: # solid breeder (HCPB); always for ipowerflow=0 - fwbs_variables.m_blkt_li2o = ( - fwbs_variables.vol_blkt_total * fwbs_variables.fblli2o * 2010.0e0 - ) - fwbs_variables.m_blkt_beryllium = ( - fwbs_variables.vol_blkt_total * fwbs_variables.fblbe * 1850.0e0 - ) - fwbs_variables.m_blkt_total = ( - fwbs_variables.m_blkt_li2o + fwbs_variables.m_blkt_beryllium - ) - - fwbs_variables.m_blkt_steel_total = ( - fwbs_variables.vol_blkt_total - * fwbs_variables.den_steel - * fwbs_variables.fblss - ) - fwbs_variables.m_blkt_vanadium = ( - fwbs_variables.vol_blkt_total * 5870.0e0 * fwbs_variables.fblvd - ) - - fwbs_variables.m_blkt_total = ( - fwbs_variables.m_blkt_total - + fwbs_variables.m_blkt_steel_total - + fwbs_variables.m_blkt_vanadium - ) - - else: # volume fractions proportional to sub-assembly thicknesses - fwbs_variables.m_blkt_steel_total = fwbs_variables.den_steel * ( - fwbs_variables.vol_blkt_inboard - / build_variables.dr_blkt_inboard - * ( - build_variables.blbuith * fwbs_variables.fblss - + build_variables.blbmith * (1.0e0 - fwbs_variables.fblhebmi) - + build_variables.blbpith * (1.0e0 - fwbs_variables.fblhebpi) - ) - + fwbs_variables.vol_blkt_outboard - / build_variables.dr_blkt_outboard - * ( - build_variables.blbuoth * fwbs_variables.fblss - + build_variables.blbmoth * (1.0e0 - fwbs_variables.fblhebmo) - + build_variables.blbpoth * (1.0e0 - fwbs_variables.fblhebpo) - ) - ) - fwbs_variables.m_blkt_beryllium = ( - 1850.0e0 - * fwbs_variables.fblbe - * ( - ( - fwbs_variables.vol_blkt_inboard - * build_variables.blbuith - / build_variables.dr_blkt_inboard - ) - + ( - fwbs_variables.vol_blkt_outboard - * build_variables.blbuoth - / build_variables.dr_blkt_outboard - ) - ) - ) - fwbs_variables.whtblbreed = ( - fwbs_variables.densbreed - * fwbs_variables.fblbreed - * ( - ( - fwbs_variables.vol_blkt_inboard - * build_variables.blbuith - / build_variables.dr_blkt_inboard - ) - + ( - fwbs_variables.vol_blkt_outboard - * build_variables.blbuoth - / build_variables.dr_blkt_outboard - ) - ) - ) - fwbs_variables.m_blkt_total = ( - fwbs_variables.m_blkt_steel_total - + fwbs_variables.m_blkt_beryllium - + fwbs_variables.whtblbreed - ) - - fwbs_variables.f_a_blkt_cooling_channels = ( - fwbs_variables.vol_blkt_inboard - / fwbs_variables.vol_blkt_total - * ( # inboard portion - (build_variables.blbuith / build_variables.dr_blkt_inboard) - * ( - 1.0e0 - - fwbs_variables.fblbe - - fwbs_variables.fblbreed - - fwbs_variables.fblss - ) - + (build_variables.blbmith / build_variables.dr_blkt_inboard) - * fwbs_variables.fblhebmi - + (build_variables.blbpith / build_variables.dr_blkt_inboard) - * fwbs_variables.fblhebpi - ) - ) - fwbs_variables.f_a_blkt_cooling_channels = ( - fwbs_variables.f_a_blkt_cooling_channels - + fwbs_variables.vol_blkt_outboard - / fwbs_variables.vol_blkt_total - * ( # outboard portion - (build_variables.blbuoth / build_variables.dr_blkt_outboard) - * ( - 1.0e0 - - fwbs_variables.fblbe - - fwbs_variables.fblbreed - - fwbs_variables.fblss - ) - + (build_variables.blbmoth / build_variables.dr_blkt_outboard) - * fwbs_variables.fblhebmo - + (build_variables.blbpoth / build_variables.dr_blkt_outboard) - * fwbs_variables.fblhebpo - ) - ) - - # When fwbs_variables.blktmodel > 0, although the blanket is by definition helium-cooled - # in this case, the shield etc. are assumed to be water-cooled, and since - # water is heavier the calculation for fwbs_variables.m_fw_blkt_div_coolant_total is better done with - # i_blkt_coolant_type=2 if fwbs_variables.blktmodel > 0; thus we can ignore the helium coolant mass - # in the blanket. - - if fwbs_variables.blktmodel == 0: - coolvol = ( - coolvol - + fwbs_variables.vol_blkt_total - * fwbs_variables.f_a_blkt_cooling_channels - ) - - # Shield mass - fwbs_variables.whtshld = ( - fwbs_variables.vol_shld_total - * fwbs_variables.den_steel - * (1.0e0 - fwbs_variables.vfshld) - ) - - coolvol = coolvol + fwbs_variables.vol_shld_total * fwbs_variables.vfshld - - # Penetration shield (set = internal shield) - - fwbs_variables.wpenshld = fwbs_variables.whtshld - - if heat_transport_variables.ipowerflow == 0: - # First wall mass - # (first wall area is calculated else:where) - - fwbs_variables.m_fw_total = ( - build_variables.a_fw_total - * (build_variables.dr_fw_inboard + build_variables.dr_fw_outboard) - / 2.0e0 - * fwbs_variables.den_steel - * (1.0e0 - fwbs_variables.fwclfr) - ) - - # Surface areas adjacent to plasma - - coolvol = ( - coolvol - + build_variables.a_fw_total - * (build_variables.dr_fw_inboard + build_variables.dr_fw_outboard) - / 2.0e0 - * fwbs_variables.fwclfr - ) - - else: - fwbs_variables.m_fw_total = fwbs_variables.den_steel * ( - build_variables.a_fw_inboard - * build_variables.dr_fw_inboard - * (1.0e0 - f_a_fw_coolant_inboard) - + build_variables.a_fw_outboard - * build_variables.dr_fw_outboard - * (1.0e0 - f_a_fw_coolant_outboard) - ) - coolvol = ( - coolvol - + build_variables.a_fw_inboard - * build_variables.dr_fw_inboard - * f_a_fw_coolant_inboard - + build_variables.a_fw_outboard - * build_variables.dr_fw_outboard - * f_a_fw_coolant_outboard - ) - - # Average first wall coolant fraction, only used by old routines - # in fispact.f90, safety.f90 - - fwbs_variables.fwclfr = ( - build_variables.a_fw_inboard - * build_variables.dr_fw_inboard - * f_a_fw_coolant_inboard - + build_variables.a_fw_outboard - * build_variables.dr_fw_outboard - * f_a_fw_coolant_outboard - ) / ( - build_variables.a_fw_total - * 0.5e0 - * (build_variables.dr_fw_inboard + build_variables.dr_fw_outboard) - ) - - # Mass of coolant = volume * density at typical coolant - # temperatures and pressures - # N.B. for fwbs_variables.blktmodel > 0, mass of *water* coolant in the non-blanket - # structures is used (see comment above) - - if (fwbs_variables.blktmodel > 0) or ( - fwbs_variables.i_blkt_coolant_type == 2 - ): # pressurised water coolant - fwbs_variables.m_fw_blkt_div_coolant_total = coolvol * 806.719e0 - else: # gaseous helium coolant - fwbs_variables.m_fw_blkt_div_coolant_total = coolvol * 1.517e0 - - # Assume external cryostat is a torus with circular cross-section, - # centred on plasma major radius. - # N.B. No check made to see if coils etc. lie wholly within cryostat... - - # External cryostat outboard major radius (m) - - fwbs_variables.r_cryostat_inboard = ( - build_variables.r_tf_outboard_mid - + 0.5e0 * build_variables.dr_tf_outboard - + fwbs_variables.dr_pf_cryostat - ) - adewex = fwbs_variables.r_cryostat_inboard - physics_variables.rmajor - - # External cryostat volume - - fwbs_variables.vol_cryostat = ( - 4.0e0 - * (np.pi**2) - * physics_variables.rmajor - * adewex - * build_variables.dr_cryostat - ) - - # Internal vacuum vessel volume - # fwbs_variables.fvoldw accounts for ports, support, etc. additions - - r1 = physics_variables.rminor + 0.5e0 * ( - build_variables.dr_fw_plasma_gap_inboard - + build_variables.dr_fw_inboard - + build_variables.dr_blkt_inboard - + build_variables.dr_shld_inboard - + build_variables.dr_fw_plasma_gap_outboard - + build_variables.dr_fw_outboard - + build_variables.dr_blkt_outboard - + build_variables.dr_shld_outboard - ) - fwbs_variables.vol_vv = ( - (build_variables.dr_vv_inboard + build_variables.dr_vv_outboard) - / 2.0e0 - * physics_variables.a_plasma_surface - * r1 - / physics_variables.rminor - * fwbs_variables.fvoldw - ) - - # Vacuum vessel mass - - fwbs_variables.m_vv = fwbs_variables.vol_vv * fwbs_variables.den_steel - - # Sum of internal vacuum vessel and external cryostat masses - - fwbs_variables.dewmkg = ( - fwbs_variables.vol_vv + fwbs_variables.vol_cryostat - ) * fwbs_variables.den_steel - - if output: - # Output section - - po.oheadr(self.outfile, "First Wall / Blanket / Shield") - po.ovarre( - self.outfile, - "Average neutron wall load (MW/m2)", - "(pflux_fw_neutron_mw)", - physics_variables.pflux_fw_neutron_mw, - ) - if fwbs_variables.blktmodel > 0: - po.ovarre( - self.outfile, - "Neutron wall load peaking factor", - "(wallpf)", - fwbs_variables.wallpf, - ) - - po.ovarre( - self.outfile, - "First wall full-power lifetime (years)", - "(life_fw_fpy)", - fwbs_variables.life_fw_fpy, - ) - - po.ovarre( - self.outfile, - "Inboard shield thickness (m)", - "(dr_shld_inboard)", - build_variables.dr_shld_inboard, - ) - po.ovarre( - self.outfile, - "Outboard shield thickness (m)", - "(dr_shld_outboard)", - build_variables.dr_shld_outboard, - ) - po.ovarre( - self.outfile, - "Top shield thickness (m)", - "(dz_shld_upper)", - build_variables.dz_shld_upper, - ) - - if fwbs_variables.blktmodel > 0: - po.ovarre( - self.outfile, - "Inboard breeding zone thickness (m)", - "(blbuith)", - build_variables.blbuith, - ) - po.ovarre( - self.outfile, - "Inboard box manifold thickness (m)", - "(blbmith)", - build_variables.blbmith, - ) - po.ovarre( - self.outfile, - "Inboard back plate thickness (m)", - "(blbpith)", - build_variables.blbpith, - ) - - po.ovarre( - self.outfile, - "Inboard blanket thickness (m)", - "(dr_blkt_inboard)", - build_variables.dr_blkt_inboard, - ) - if fwbs_variables.blktmodel > 0: - po.ovarre( - self.outfile, - "Outboard breeding zone thickness (m)", - "(blbuoth)", - build_variables.blbuoth, - ) - po.ovarre( - self.outfile, - "Outboard box manifold thickness (m)", - "(blbmoth)", - build_variables.blbmoth, - ) - po.ovarre( - self.outfile, - "Outboard back plate thickness (m)", - "(blbpoth)", - build_variables.blbpoth, - ) - - po.ovarre( - self.outfile, - "Outboard blanket thickness (m)", - "(dr_blkt_outboard)", - build_variables.dr_blkt_outboard, - ) - po.ovarre( - self.outfile, - "Top blanket thickness (m)", - "(dz_blkt_upper)", - build_variables.dz_blkt_upper, - ) - - if (heat_transport_variables.ipowerflow == 0) and ( - fwbs_variables.blktmodel == 0 - ): - po.osubhd(self.outfile, "Coil nuclear parameters :") - po.ovarre( - self.outfile, "Peak magnet heating (MW/m3)", "(coilhtmx)", coilhtmx - ) - po.ovarre( - self.outfile, - "Inboard coil winding pack heating (MW)", - "(ptfiwp)", - ptfiwp, - ) - po.ovarre( - self.outfile, - "Outboard coil winding pack heating (MW)", - "(ptfowp)", - ptfowp, - ) - po.ovarre( - self.outfile, "Peak coil case heating (MW/m3)", "(htheci)", htheci - ) - po.ovarre( - self.outfile, "Inboard coil case heating (MW)", "(pheci)", pheci - ) - po.ovarre( - self.outfile, "Outboard coil case heating (MW)", "(pheco)", pheco - ) - po.ovarre(self.outfile, "Insulator dose (rad)", "(raddose)", raddose) - po.ovarre( - self.outfile, - "Maximum neutron fluence (n/m2)", - "(nflutf)", - fwbs_variables.nflutf, - ) - po.ovarre( - self.outfile, - "Copper stabiliser displacements/atom", - "(dpacop)", - dpacop, - ) - - if fwbs_variables.blktmodel == 0: - po.osubhd(self.outfile, "Nuclear heating :") - po.ovarre( - self.outfile, - "Blanket heating (including energy multiplication) (MW)", - "(p_blkt_nuclear_heat_total_mw)", - fwbs_variables.p_blkt_nuclear_heat_total_mw, - ) - po.ovarre( - self.outfile, - "Shield nuclear heating (MW)", - "(p_shld_nuclear_heat_mw)", - fwbs_variables.p_shld_nuclear_heat_mw, - ) - po.ovarre( - self.outfile, - "Coil nuclear heating (MW)", - "(p_tf_nuclear_heat_mw)", - fwbs_variables.p_tf_nuclear_heat_mw, - ) - else: - po.osubhd(self.outfile, "Blanket neutronics :") - po.ovarre( - self.outfile, - "Blanket heating (including energy multiplication) (MW)", - "(p_blkt_nuclear_heat_total_mw)", - fwbs_variables.p_blkt_nuclear_heat_total_mw, - ) - po.ovarre( - self.outfile, - "Shield heating (MW)", - "(p_shld_nuclear_heat_mw)", - fwbs_variables.p_shld_nuclear_heat_mw, - ) - po.ovarre( - self.outfile, - "Energy multiplication in blanket", - "(f_p_blkt_multiplication)", - fwbs_variables.f_p_blkt_multiplication, - ) - po.ovarin( - self.outfile, - "Number of divertor ports assumed", - "(npdiv)", - fwbs_variables.npdiv, - ) - po.ovarin( - self.outfile, - "Number of inboard H/CD ports assumed", - "(nphcdin)", - fwbs_variables.nphcdin, - ) - po.ovarin( - self.outfile, - "Number of outboard H/CD ports assumed", - "(nphcdout)", - fwbs_variables.nphcdout, - ) - if fwbs_variables.hcdportsize == 1: - po.ocmmnt( - self.outfile, " (small heating/current drive ports assumed)" - ) - else: - po.ocmmnt( - self.outfile, " (large heating/current drive ports assumed)" - ) - - if fwbs_variables.breedmat == 1: - po.ocmmnt( - self.outfile, - "Breeder material: Lithium orthosilicate (Li4Si04)", - ) - elif fwbs_variables.breedmat == 2: - po.ocmmnt( - self.outfile, - "Breeder material: Lithium methatitanate (Li2TiO3)", - ) - elif fwbs_variables.breedmat == 3: - po.ocmmnt( - self.outfile, "Breeder material: Lithium zirconate (Li2ZrO3)" - ) - else: # shouldn't get here... - po.ocmmnt(self.outfile, "Unknown breeder material...") - - po.ovarre( - self.outfile, - "Lithium-6 enrichment (%)", - "(f_blkt_li6_enrichment)", - fwbs_variables.f_blkt_li6_enrichment, - ) - po.ovarre( - self.outfile, - "Tritium production rate (g/day)", - "(tritprate)", - fwbs_variables.tritprate, - ) - po.ovarre( - self.outfile, - "Nuclear heating on i/b coil (MW/m3)", - "(pnuctfi)", - fwbs_variables.pnuctfi, - ) - po.ovarre( - self.outfile, - "Nuclear heating on o/b coil (MW/m3)", - "(pnuctfo)", - fwbs_variables.pnuctfo, - ) - po.ovarre( - self.outfile, - "Total nuclear heating on coil (MW)", - "(p_tf_nuclear_heat_mw)", - fwbs_variables.p_tf_nuclear_heat_mw, - ) - po.ovarre( - self.outfile, - "Fast neut. fluence on i/b coil (n/m2)", - "(nflutfi)", - fwbs_variables.nflutfi * 1.0e4, - ) - po.ovarre( - self.outfile, - "Fast neut. fluence on o/b coil (n/m2)", - "(nflutfo)", - fwbs_variables.nflutfo * 1.0e4, - ) - po.ovarre( - self.outfile, - "Minimum final He conc. in IB VV (appm)", - "(vvhemini)", - fwbs_variables.vvhemini, - ) - po.ovarre( - self.outfile, - "Minimum final He conc. in OB VV (appm)", - "(vvhemino)", - fwbs_variables.vvhemino, - ) - po.ovarre( - self.outfile, - "Maximum final He conc. in IB VV (appm)", - "(vvhemaxi)", - fwbs_variables.vvhemaxi, - ) - po.ovarre( - self.outfile, - "Maximum final He conc. in OB VV (appm)", - "(vvhemaxo)", - fwbs_variables.vvhemaxo, - ) - po.ovarre( - self.outfile, - "Blanket lifetime (full power years)", - "(life_blkt_fpy)", - fwbs_variables.life_blkt_fpy, - ) - po.ovarre( - self.outfile, - "Blanket lifetime (calendar years)", - "(t_bl_y)", - fwbs_variables.t_bl_y, - ) - - if (heat_transport_variables.ipowerflow == 1) and ( - fwbs_variables.blktmodel == 0 - ): - po.oblnkl(self.outfile) - po.ovarin( - self.outfile, - "First wall / blanket thermodynamic model", - "(i_thermal_electric_conversion)", - fwbs_variables.i_thermal_electric_conversion, - ) - if fwbs_variables.i_thermal_electric_conversion == 0: - po.ocmmnt(self.outfile, " (Simple calculation)") - - po.osubhd(self.outfile, "Blanket / shield volumes and weights :") - - # if (fwbs_variables.blktmodel == 0) : - # if ((fwbs_variables.blkttype == 1)or(fwbs_variables.blkttype == 2)) : - # po.write(self.outfile,601) vol_blkt_inboard, vol_blkt_outboard, vol_blkt_total, m_blkt_total, f_a_blkt_cooling_channels, fbllipb, wtbllipb, fblli, m_blkt_lithium, fblss, m_blkt_steel_total, fblvd, m_blkt_vanadium, vol_shld_inboard, vol_shld_outboard, vol_shld_total, whtshld, vfshld, fwbs_variables.wpenshld - # else: # (also if ipowerflow=0) - # po.write(self.outfile,600) vol_blkt_inboard, vol_blkt_outboard, vol_blkt_total, m_blkt_total, f_a_blkt_cooling_channels, fblbe, m_blkt_beryllium, fblli2o, m_blkt_li2o, fblss, m_blkt_steel_total, fblvd, m_blkt_vanadium, vol_shld_inboard, vol_shld_outboard, vol_shld_total, whtshld, vfshld, fwbs_variables.wpenshld - - # else: - # po.write(self.outfile,602) vol_blkt_inboard, vol_blkt_outboard, vol_blkt_total, m_blkt_total, f_a_blkt_cooling_channels, (fwbs_variables.vol_blkt_inboard/fwbs_variables.vol_blkt_total * build_variables.blbuith/build_variables.dr_blkt_inboard + fwbs_variables.vol_blkt_outboard/fwbs_variables.vol_blkt_total * build_variables.blbuoth/build_variables.dr_blkt_outboard) * fblbe, m_blkt_beryllium, (fwbs_variables.vol_blkt_inboard/fwbs_variables.vol_blkt_total * build_variables.blbuith/build_variables.dr_blkt_inboard + fwbs_variables.vol_blkt_outboard/fwbs_variables.vol_blkt_total * build_variables.blbuoth/build_variables.dr_blkt_outboard) * fblbreed, whtblbreed, fwbs_variables.vol_blkt_inboard/fwbs_variables.vol_blkt_total/build_variables.dr_blkt_inboard * (build_variables.blbuith * fwbs_variables.fblss + build_variables.blbmith * (1.0e0-fwbs_variables.fblhebmi) + build_variables.blbpith * (1.0e0-fwbs_variables.fblhebpi)) + fwbs_variables.vol_blkt_outboard/fwbs_variables.vol_blkt_total/build_variables.dr_blkt_outboard * (build_variables.blbuoth * fwbs_variables.fblss + build_variables.blbmoth * (1.0e0-fwbs_variables.fblhebmo) + build_variables.blbpoth * (1.0e0-fwbs_variables.fblhebpo)), m_blkt_steel_total, vol_shld_inboard, vol_shld_outboard, vol_shld_total, whtshld, vfshld, fwbs_variables.wpenshld - - # 600 format( t32,'volume (m3)',t45,'vol fraction',t62,'weight (kg)'/ t32,'-----------',t45,'------------',t62,'-----------'/ ' Inboard blanket' ,t32,1pe10.3,/ ' Outboard blanket' ,t32,1pe10.3,/ ' Total blanket' ,t32,1pe10.3,t62,1pe10.3/ ' Void fraction' ,t45,1pe10.3,/ ' Blanket Be ',t45,1pe10.3,t62,1pe10.3/ ' Blanket Li2O ',t45,1pe10.3,t62,1pe10.3/ ' Blanket ss ',t45,1pe10.3,t62,1pe10.3/ ' Blanket Vd ',t45,1pe10.3,t62,1pe10.3/ ' Inboard shield' ,t32,1pe10.3,/ ' Outboard shield' ,t32,1pe10.3,/ ' Primary shield',t32,1pe10.3,t62,1pe10.3/ ' Void fraction' ,t45,1pe10.3,/ ' Penetration shield' ,t62,1pe10.3) - - # 601 format( t32,'volume (m3)',t45,'vol fraction',t62,'weight (kg)'/ t32,'-----------',t45,'------------',t62,'-----------'/ ' Inboard blanket' ,t32,1pe10.3,/ ' Outboard blanket' ,t32,1pe10.3,/ ' Total blanket' ,t32,1pe10.3,t62,1pe10.3/ ' Void fraction' ,t45,1pe10.3,/ ' Blanket LiPb ',t45,1pe10.3,t62,1pe10.3/ ' Blanket Li ',t45,1pe10.3,t62,1pe10.3/ ' Blanket ss ',t45,1pe10.3,t62,1pe10.3/ ' Blanket Vd ',t45,1pe10.3,t62,1pe10.3/ ' Inboard shield' ,t32,1pe10.3,/ ' Outboard shield' ,t32,1pe10.3,/ ' Primary shield',t32,1pe10.3,t62,1pe10.3/ ' Void fraction' ,t45,1pe10.3,/ ' Penetration shield' ,t62,1pe10.3) - - # 602 format( t32,'volume (m3)',t45,'vol fraction',t62,'weight (kg)'/ t32,'-----------',t45,'------------',t62,'-----------'/ ' Inboard blanket' ,t32,1pe10.3,/ ' Outboard blanket' ,t32,1pe10.3,/ ' Total blanket' ,t32,1pe10.3,t62,1pe10.3/ ' Void fraction' ,t45,1pe10.3,/ ' Blanket Be ',t45,1pe10.3,t62,1pe10.3/ ' Blanket breeder',t45,1pe10.3,t62,1pe10.3/ ' Blanket steel',t45,1pe10.3,t62,1pe10.3/ ' Inboard shield' ,t32,1pe10.3,/ ' Outboard shield' ,t32,1pe10.3,/ ' Primary shield',t32,1pe10.3,t62,1pe10.3/ ' Void fraction' ,t45,1pe10.3,/ ' Penetration shield' ,t62,1pe10.3) - - po.osubhd(self.outfile, "Other volumes, masses and areas :") - po.ovarre( - self.outfile, - "First wall area (m2)", - "(a_fw_total)", - build_variables.a_fw_total, - ) - po.ovarre( - self.outfile, - "First wall mass (kg)", - "(m_fw_total)", - fwbs_variables.m_fw_total, - ) - po.ovarre( - self.outfile, - "External cryostat inner radius (m)", - "", - fwbs_variables.r_cryostat_inboard - 2.0e0 * adewex, - ) - po.ovarre( - self.outfile, - "External cryostat outer radius (m)", - "(r_cryostat_inboard)", - fwbs_variables.r_cryostat_inboard, - ) - po.ovarre( - self.outfile, "External cryostat minor radius (m)", "(adewex)", adewex - ) - po.ovarre( - self.outfile, - "External cryostat shell volume (m^3)", - "(vol_cryostat)", - fwbs_variables.vol_cryostat, - ) - po.ovarre( - self.outfile, - "Internal volume of the cryostat structure (m^3)", - "(vol_cryostat_internal)", - fwbs_variables.vol_cryostat_internal, - ) - po.ovarre( - self.outfile, - "External cryostat mass (kg)", - "", - fwbs_variables.dewmkg - fwbs_variables.m_vv, - ) - po.ovarre( - self.outfile, - "Internal vacuum vessel shell volume (m3)", - "(vol_vv)", - fwbs_variables.vol_vv, - ) - po.ovarre( - self.outfile, - "Vacuum vessel mass (kg)", - "(m_vv)", - fwbs_variables.m_vv, - ) - po.ovarre( - self.outfile, - "Total cryostat + vacuum vessel mass (kg)", - "(dewmkg)", - fwbs_variables.dewmkg, - ) - po.ovarre( - self.outfile, - "Divertor area (m2)", - "(a_div_surface_total)", - divertor_variables.a_div_surface_total, - ) - po.ovarre( - self.outfile, - "Divertor mass (kg)", - "(m_div_plate)", - divertor_variables.m_div_plate, - ) - - def sctfcoil_nuclear_heating_iter90(self): - """Superconducting TF coil nuclear heating estimate - author: P J Knight, CCFE, Culham Science Centre - coilhtmx : output real : peak magnet heating (MW/m3) - dpacop : output real : copper stabiliser displacements/atom - htheci : output real : peak TF coil case heating (MW/m3) - nflutf : output real : maximum neutron fluence (n/m2) - pheci : output real : inboard coil case heating (MW) - pheco : output real : outboard coil case heating (MW) - ptfiwp : output real : inboard TF coil winding pack heating (MW) - ptfowp : output real : outboard TF coil winding pack heating (MW) - raddose : output real : insulator dose (rad) - p_tf_nuclear_heat_mw : output real : TF coil nuclear heating (MW) - This subroutine calculates the nuclear heating in the - superconducting TF coils, assuming an exponential neutron - attenuation through the blanket and shield materials. - The estimates are based on 1990 ITER data. -

The arrays coef(i,j) and decay(i,j) - are used for exponential decay approximations of the - (superconducting) TF coil nuclear parameters. -

- Note: Costing and mass calculations elsewhere assume - stainless steel only. - """ - - ishmat = 0 # stainless steel coil casing is assumed - - if tfcoil_variables.i_tf_sup != 1: # Resistive coils - coilhtmx = 0.0 - ptfiwp = 0.0 - ptfowp = 0.0 - htheci = 0.0 - pheci = 0.0 - pheco = 0.0 - raddose = 0.0 - nflutf = 0.0 - dpacop = 0.0 - p_tf_nuclear_heat_mw = 0.0 - - else: - # TF coil nuclear heating coefficients in region i (first element), - # assuming shield material j (second element where present) - - fact = np.array([8.0, 8.0, 6.0, 4.0, 4.0]) - coef = np.array([ - [10.3, 11.6, 7.08e5, 2.19e18, 3.33e-7], - [8.32, 10.6, 7.16e5, 2.39e18, 3.84e-7], - ]).T - - decay = np.array([ - [10.05, 17.61, 13.82, 13.24, 14.31, 13.26, 13.25], - [10.02, 3.33, 15.45, 14.47, 15.87, 15.25, 17.25], - ]).T - - # N.B. The vacuum vessel appears to be ignored - - dshieq = ( - build_variables.dr_shld_inboard - + build_variables.dr_fw_inboard - + build_variables.dr_blkt_inboard - ) - dshoeq = ( - build_variables.dr_shld_outboard - + build_variables.dr_fw_outboard - + build_variables.dr_blkt_outboard - ) - - # Winding pack radial thickness, including groundwall insulation - - wpthk = ( - tfcoil_variables.dr_tf_wp_with_insulation - + 2.0 * tfcoil_variables.dx_tf_wp_insulation - ) - - # Nuclear heating rate in inboard TF coil (MW/m**3) - - coilhtmx = ( - fact[0] - * physics_variables.pflux_fw_neutron_mw - * coef[0, ishmat] - * np.exp( - -decay[5, ishmat] * (dshieq + tfcoil_variables.dr_tf_plasma_case) - ) - ) - - # Total nuclear heating (MW) - - ptfiwp = ( - coilhtmx - * tfcoil_variables.tfsai - * (1.0 - np.exp(-decay[0, ishmat] * wpthk)) - / decay[0, ishmat] - ) - ptfowp = ( - fact[0] - * physics_variables.pflux_fw_neutron_mw - * coef[0, ishmat] - * np.exp( - -decay[5, ishmat] * (dshoeq + tfcoil_variables.dr_tf_plasma_case) - ) - * tfcoil_variables.tfsao - * (1.0 - np.exp(-decay[0, ishmat] * wpthk)) - / decay[0, ishmat] - ) - - # Nuclear heating in plasma-side TF coil case (MW) - - htheci = ( - fact[1] - * physics_variables.pflux_fw_neutron_mw - * coef[1, ishmat] - * np.exp(-decay[6, ishmat] * dshieq) - ) - pheci = ( - htheci - * tfcoil_variables.tfsai - * (1.0 - np.exp(-decay[1, ishmat] * tfcoil_variables.dr_tf_plasma_case)) - / decay[1, ishmat] - ) - pheco = ( - fact[1] - * physics_variables.pflux_fw_neutron_mw - * coef[1, ishmat] - * np.exp(-decay[6, ishmat] * dshoeq) - * tfcoil_variables.tfsao - * (1.0 - np.exp(-decay[1, ishmat] * tfcoil_variables.dr_tf_plasma_case)) - / decay[1, ishmat] - ) - ptfi = ptfiwp + pheci - ptfo = ptfowp + pheco - - p_tf_nuclear_heat_mw = ptfi + ptfo - - # Full power DT operation years for replacement of TF Coil - # (or plant life) - - fpydt = cost_variables.f_t_plant_available * cost_variables.life_plant - fpsdt = fpydt * 3.154e7 # seconds - - # Insulator dose (rad) - - raddose = ( - coef[2, ishmat] - * fpsdt - * fact[2] - * physics_variables.pflux_fw_neutron_mw - * np.exp( - -decay[2, ishmat] * (dshieq + tfcoil_variables.dr_tf_plasma_case) - ) - ) - - # Maximum neutron fluence in superconductor (n/m**2) - - nflutf = ( - fpsdt - * fact[3] - * physics_variables.pflux_fw_neutron_mw - * coef[3, ishmat] - * np.exp( - -decay[3, ishmat] * (dshieq + tfcoil_variables.dr_tf_plasma_case) - ) - ) - - # Atomic displacement in copper stabilizer - - dpacop = ( - fpsdt - * fact[4] - * physics_variables.pflux_fw_neutron_mw - * coef[4, ishmat] - * np.exp( - -decay[4, ishmat] * (dshieq + tfcoil_variables.dr_tf_plasma_case) - ) - ) - - return ( - coilhtmx, - dpacop, - htheci, - nflutf, - pheci, - pheco, - ptfiwp, - ptfowp, - raddose, - p_tf_nuclear_heat_mw, - ) - - def stcoil(self, output: bool): - """Routine that performs the calculations for stellarator coils - author: J Lion, IPP Greifswald - outfile : input integer : output file unit - iprint : input integer : switch for writing to output file (1=yes) - This routine calculates the properties of the coils for - a stellarator device. -

Some precalculated effective parameters for a stellarator power - plant design are used as the basis for the calculations. The coils - are assumed to be a fixed shape, but are scaled in size - appropriately for the machine being modelled. - """ - r_coil_major = ( - stellarator_configuration.stella_config_coil_rmajor - * stellarator_variables.f_r - ) - r_coil_minor = ( - stellarator_configuration.stella_config_coil_rminor - * stellarator_variables.f_r - ) - - ######################################################################################## - # Winding Pack Geometry: for one conductor - # - # This one conductor will just be multiplied later to fit the winding pack size. - # - # [m] Dimension of square cable space inside insulation - # and case of the conduit of each turn - dx_tf_turn_cable_space_average = tfcoil_variables.dx_tf_turn_general - 2.0e0 * ( - tfcoil_variables.dx_tf_turn_steel + tfcoil_variables.dx_tf_turn_insulation - ) # dx_tf_turn_cable_space_average = t_w - if dx_tf_turn_cable_space_average < 0: - print( - "dx_tf_turn_cable_space_average is negative. Check t_turn, tfcoil_variables.dx_tf_turn_steel and dx_tf_turn_insulation." - ) - # [m^2] Cross-sectional area of cable space per turn - tfcoil_variables.a_tf_turn_cable_space_no_void = ( - 0.9e0 * dx_tf_turn_cable_space_average**2 - ) # 0.9 to include some rounded corners. (tfcoil_variables.a_tf_turn_cable_space_no_void = pi (dx_tf_turn_cable_space_average/2)**2 = pi/4 *dx_tf_turn_cable_space_average**2 for perfect round conductor). This factor depends on how round the corners are. - # [m^2] Cross-sectional area of conduit case per turn - tfcoil_variables.a_tf_turn_steel = ( - dx_tf_turn_cable_space_average + 2.0e0 * tfcoil_variables.dx_tf_turn_steel - ) ** 2 - tfcoil_variables.a_tf_turn_cable_space_no_void - ####################################################################################### - - ####################################################################################### - # Winding Pack total size: - # - # Total coil current (MA) - coilcurrent = ( - stellarator_variables.f_b - * stellarator_configuration.stella_config_i0 - * stellarator_variables.f_r - / stellarator_variables.f_n - ) - stellarator_variables.f_i = ( - coilcurrent / stellarator_configuration.stella_config_i0 - ) - - n_it = 200 # number of iterations - - rhs = np.zeros((n_it,)) - lhs = np.zeros((n_it,)) - jcrit_vector = np.zeros((n_it,)) - wp_width_r = np.zeros((n_it,)) - b_max_k = np.zeros((n_it,)) - - for k in range(n_it): - # Sample coil winding pack - wp_width_r[k] = (r_coil_minor / 40.0e0) + (k / (n_it - 1e0)) * ( - r_coil_minor / 1.0e0 - r_coil_minor / 40.0e0 - ) - if tfcoil_variables.i_tf_sc_mat == 6: - wp_width_r[k] = (r_coil_minor / 150.0e0) + (k / (n_it - 1e0)) * ( - r_coil_minor / 1.0e0 - r_coil_minor / 150.0e0 - ) - - # B-field calculation - b_max_k[k] = self.bmax_from_awp( - wp_width_r[k], - coilcurrent, - tfcoil_variables.n_tf_coils, - r_coil_major, - r_coil_minor, - ) - - # jcrit for this bmax: - jcrit_vector[k] = self.jcrit_frommaterial( - b_max_k[k], - tfcoil_variables.tftmp + 1.5, - tfcoil_variables.i_tf_sc_mat, - tfcoil_variables.b_crit_upper_nbti, - tfcoil_variables.bcritsc, - tfcoil_variables.f_a_tf_turn_cable_copper, - tfcoil_variables.fhts, - tfcoil_variables.t_crit_nbti, - tfcoil_variables.tcritsc, - tfcoil_variables.f_a_tf_turn_cable_space_extra_void, - tfcoil_variables.j_tf_wp, - ) # Get here a temperature margin of 1.5K. - - # The operation current density weighted with the global iop/icrit fraction - lhs[:] = constraint_variables.fiooic * jcrit_vector - - # Conduct fraction of conduit * Superconductor fraction in conductor - f_scu = ( - ( - tfcoil_variables.a_tf_turn_cable_space_no_void - * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void) - ) - / (tfcoil_variables.dx_tf_turn_general**2) - * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_copper) - ) # fraction that is SC of wp. - # print *, "f_scu. ",f_scu,"Awp min: ",Awp(1) - - rhs[:] = coilcurrent / ( - wp_width_r**2 / stellarator_configuration.stella_config_wp_ratio * f_scu - ) # f_scu should be the fraction of the sc that is in the winding pack. - - wp_width_r_min = ( - r_coil_minor / 10.0e0 - ) ** 2 # Initial guess for intersection routine - if tfcoil_variables.i_tf_sc_mat == 6: - wp_width_r_min = ( - r_coil_minor / 20.0e0 - ) ** 2 # If REBCO, : start at smaller winding pack ratios - - # Find the intersection between LHS and RHS (or: how much awp do I need to get to the desired coil current) - wp_width_r_min = self.intersect(wp_width_r, lhs, wp_width_r, rhs, wp_width_r_min) - - # Maximum field at superconductor surface (T) - wp_width_r_min = max(tfcoil_variables.dx_tf_turn_general**2, wp_width_r_min) - - # Recalculate tfcoil_variables.b_tf_inboard_peak_symmetric at the found awp_min: - tfcoil_variables.b_tf_inboard_peak_symmetric = self.bmax_from_awp( - wp_width_r_min, - coilcurrent, - tfcoil_variables.n_tf_coils, - r_coil_major, - r_coil_minor, - ) - - # Winding pack toroidal, radial cross-sections (m) - awp_tor = ( - wp_width_r_min / stellarator_configuration.stella_config_wp_ratio - ) # Toroidal dimension - awp_rad = wp_width_r_min # Radial dimension - - tfcoil_variables.dx_tf_wp_primary_toroidal = ( - awp_tor # [m] toroidal thickness of winding pack - ) - tfcoil_variables.dx_tf_wp_secondary_toroidal = ( - awp_tor # [m] toroidal thickness of winding pack (region in front) - ) - tfcoil_variables.dr_tf_wp_with_insulation = ( - awp_rad # [m] radial thickness of winding pack - ) - - # [m^2] winding-pack cross sectional area including insulation (not global) - a_tf_wp_with_insulation = ( - tfcoil_variables.dr_tf_wp_with_insulation - + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation - ) * ( - tfcoil_variables.dx_tf_wp_primary_toroidal - + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation - ) - - a_tf_wp_no_insulation = ( - awp_tor * awp_rad - ) # [m^2] winding-pack cross sectional area - tfcoil_variables.j_tf_wp = ( - coilcurrent * 1.0e6 / a_tf_wp_no_insulation - ) # [A/m^2] winding pack current density - tfcoil_variables.n_tf_coil_turns = ( - a_tf_wp_no_insulation / (tfcoil_variables.dx_tf_turn_general**2) - ) # estimated number of turns for a given turn size (not global). Take at least 1. - tfcoil_variables.c_tf_turn = ( - coilcurrent * 1.0e6 / tfcoil_variables.n_tf_coil_turns - ) # [A] current per turn - estimation - # [m^2] Total conductor cross-sectional area, taking account of void area - tfcoil_variables.a_tf_wp_conductor = ( - tfcoil_variables.a_tf_turn_cable_space_no_void - * tfcoil_variables.n_tf_coil_turns - * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void) - ) - # [m^2] Void area in cable, for He - tfcoil_variables.a_tf_wp_extra_void = ( - tfcoil_variables.a_tf_turn_cable_space_no_void - * tfcoil_variables.n_tf_coil_turns - * tfcoil_variables.f_a_tf_turn_cable_space_extra_void - ) - # [m^2] Insulation area (not including ground-wall) - tfcoil_variables.a_tf_coil_wp_turn_insulation = ( - tfcoil_variables.n_tf_coil_turns - * ( - tfcoil_variables.dx_tf_turn_general**2 - - tfcoil_variables.a_tf_turn_steel - - tfcoil_variables.a_tf_turn_cable_space_no_void - ) - ) - # [m^2] Structure area for cable - tfcoil_variables.a_tf_wp_steel = ( - tfcoil_variables.n_tf_coil_turns * tfcoil_variables.a_tf_turn_steel - ) - # End of winding pack calculations - ####################################################################################### - - ####################################################################################### - # Casing calculations - # - # Coil case thickness (m). Here assumed to be constant - # until something better comes up. - # case_thickness_constant = tfcoil_variables.dr_tf_nose_case #0.2e0 # #? Leave this constant for now... Check this## Should be scaled with forces I think. - # For now assumed to be constant in a bolted plate model. - # - tfcoil_variables.dr_tf_plasma_case = ( - tfcoil_variables.dr_tf_nose_case - ) # [m] coil case thickness outboard distance (radial) - # dr_tf_nose_case = case_thickness_constant/2.0e0 # [m] coil case thickness inboard distance (radial). - tfcoil_variables.dx_tf_side_case_min = ( - tfcoil_variables.dr_tf_nose_case - ) # [m] coil case thickness toroidal distance (toroidal) - - # End of casing calculations - ####################################################################################### - - ####################################################################################### - # Port calculations - # - # Maximal toroidal port size (vertical ports) (m) - # The maximal distance is correct but the vertical extension of this port is not clear# - # This is simplified for now and can be made more accurate in the future# - stellarator_variables.vporttmax = ( - 0.4e0 - * stellarator_configuration.stella_config_max_portsize_width - * stellarator_variables.f_r - / stellarator_variables.f_n - ) # This is not accurate yet. Needs more insight# - - # Maximal poloidal port size (vertical ports) (m) - stellarator_variables.vportpmax = ( - 2.0 * stellarator_variables.vporttmax - ) # Simple approximation - - # Maximal vertical port clearance area (m2) - stellarator_variables.vportamax = ( - stellarator_variables.vporttmax * stellarator_variables.vportpmax - ) - - # Horizontal ports - # Maximal toroidal port size (horizontal ports) (m) - stellarator_variables.hporttmax = ( - 0.8e0 - * stellarator_configuration.stella_config_max_portsize_width - * stellarator_variables.f_r - / stellarator_variables.f_n - ) # Factor 0.8 to take the variation with height into account - - # Maximal poloidal port size (horizontal ports) (m) - stellarator_variables.hportpmax = ( - 2.0e0 * stellarator_variables.hporttmax - ) # Simple approximation - - # Maximal horizontal port clearance area (m2) - stellarator_variables.hportamax = ( - stellarator_variables.hporttmax * stellarator_variables.hportpmax - ) - # End of port calculations - ####################################################################################### - - ####################################################################################### - # General Coil Geometry values - # - tfcoil_variables.dx_tf_inboard_out_toroidal = ( - tfcoil_variables.dx_tf_wp_primary_toroidal - + 2.0e0 * tfcoil_variables.dx_tf_side_case_min - + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation - ) # [m] Thickness of inboard leg in toroidal direction - - build_variables.dr_tf_inboard = ( - tfcoil_variables.dr_tf_nose_case - + tfcoil_variables.dr_tf_wp_with_insulation - + tfcoil_variables.dr_tf_plasma_case - + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation - ) # [m] Thickness of inboard leg in radial direction - build_variables.dr_tf_outboard = ( - tfcoil_variables.dr_tf_nose_case - + tfcoil_variables.dr_tf_wp_with_insulation - + tfcoil_variables.dr_tf_plasma_case - + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation - ) # [m] Thickness of outboard leg in radial direction (same as inboard) - tfcoil_variables.a_tf_leg_outboard = ( - build_variables.dr_tf_inboard * tfcoil_variables.dx_tf_inboard_out_toroidal - ) # [m^2] overall coil cross-sectional area (assuming inboard and - # outboard leg are the same) - tfcoil_variables.a_tf_coil_inboard_case = ( - build_variables.dr_tf_inboard * tfcoil_variables.dx_tf_inboard_out_toroidal - ) - a_tf_wp_with_insulation # [m^2] Cross-sectional area of surrounding case - - tfcoil_variables.tfocrn = ( - 0.5e0 * tfcoil_variables.dx_tf_inboard_out_toroidal - ) # [m] Half-width of side of coil nearest torus centreline - tfcoil_variables.tficrn = ( - 0.5e0 * tfcoil_variables.dx_tf_inboard_out_toroidal - ) # [m] Half-width of side of coil nearest plasma - - # [m^2] Total surface area of coil side facing plasma: inboard region - tfcoil_variables.tfsai = ( - tfcoil_variables.n_tf_coils - * tfcoil_variables.dx_tf_inboard_out_toroidal - * 0.5e0 - * tfcoil_variables.len_tf_coil - ) - # [m^2] Total surface area of coil side facing plasma: outboard region - tfcoil_variables.tfsao = ( - tfcoil_variables.tfsai - ) # depends, how 'inboard' and 'outboard' are defined - - # [m] Minimal distance in toroidal direction between two stellarator coils (from mid to mid) - # Consistency with coil width is checked in constraint equation 82 - tfcoil_variables.toroidalgap = ( - stellarator_configuration.stella_config_dmin - * (r_coil_major - r_coil_minor) - / ( - stellarator_configuration.stella_config_coil_rmajor - - stellarator_configuration.stella_config_coil_rminor - ) - ) - # Left-Over coil gap between two coils (m) - coilcoilgap = ( - tfcoil_variables.toroidalgap - tfcoil_variables.dx_tf_inboard_out_toroidal - ) - - # Variables for ALL coils. - tfcoil_variables.a_tf_inboard_total = ( - tfcoil_variables.n_tf_coils * tfcoil_variables.a_tf_leg_outboard - ) # [m^2] Total area of all coil legs (midplane) - tfcoil_variables.c_tf_total = ( - tfcoil_variables.n_tf_coils * coilcurrent * 1.0e6 - ) # [A] Total current in ALL coils - tfcoil_variables.oacdcp = ( - tfcoil_variables.c_tf_total / tfcoil_variables.a_tf_inboard_total - ) # [A / m^2] overall current density - tfcoil_variables.r_b_tf_inboard_peak = ( - r_coil_major - r_coil_minor + awp_rad - ) # [m] radius of peak field occurrence, average - # jlion: not sure what this will be used for. Not very - # useful for stellarators - - # This uses the reference value for the inductance and scales it with a^2/R (toroid inductance scaling) - inductance = ( - stellarator_configuration.stella_config_inductance - / stellarator_variables.f_r - * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) ** 2 - * stellarator_variables.f_n**2 - ) - tfcoil_variables.e_tf_magnetic_stored_total_gj = ( - 0.5e0 - * ( - stellarator_configuration.stella_config_inductance - / stellarator_variables.f_r - * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) - ** 2 - * stellarator_variables.f_n**2 - ) - * (tfcoil_variables.c_tf_total / tfcoil_variables.n_tf_coils) ** 2 - * 1.0e-9 - ) # [GJ] Total magnetic energy - - # Coil dimensions - build_variables.z_tf_inside_half = ( - 0.5e0 - * stellarator_configuration.stella_config_maximal_coil_height - * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) - ) # [m] maximum half-height of coil - r_tf_inleg_mid = ( - r_coil_major - r_coil_minor - ) # This is not very well defined for a stellarator. - # Though, this is taken as an average value. - tf_total_h_width = ( - r_coil_minor # ? not really sure what this is supposed to be. Estimated as - ) - # the average minor coil radius - - tfborev = ( - 2.0e0 * build_variables.z_tf_inside_half - ) # [m] estimated vertical coil dr_bore - - tfcoil_variables.len_tf_coil = ( - stellarator_configuration.stella_config_coillength - * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) - / tfcoil_variables.n_tf_coils - ) # [m] estimated average length of a coil - - # [m^2] Total surface area of toroidal shells covering coils - tfcoil_variables.tfcryoarea = ( - stellarator_configuration.stella_config_coilsurface - * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) ** 2 - * 1.1e0 - ) # 1.1 to scale it out a bit. Should be coupled to winding pack maybe. - - # Minimal bending radius: - min_bending_radius = ( - stellarator_configuration.stella_config_min_bend_radius - * stellarator_variables.f_r - * 1.0 - / (1.0 - tfcoil_variables.dr_tf_wp_with_insulation / (2.0 * r_coil_minor)) - ) - - # End of general coil geometry values - ####################################################################################### - - ####################################################################################### - # Masses of conductor constituents - # - # [kg] Mass of case - # (no need for correction factors as is the case for tokamaks) - # This is only correct if the winding pack is 'thin' (len_tf_coil>>sqrt(tfcoil_variables.a_tf_coil_inboard_case)). - tfcoil_variables.m_tf_coil_case = ( - tfcoil_variables.len_tf_coil - * tfcoil_variables.a_tf_coil_inboard_case - * tfcoil_variables.den_tf_coil_case - ) - # Mass of ground-wall insulation [kg] - # (assumed to be same density/material as conduit insulation) - tfcoil_variables.m_tf_coil_wp_insulation = ( - tfcoil_variables.len_tf_coil - * (a_tf_wp_with_insulation - a_tf_wp_no_insulation) - * tfcoil_variables.den_tf_wp_turn_insulation - ) - # [kg] mass of Superconductor - tfcoil_variables.m_tf_coil_superconductor = ( - tfcoil_variables.len_tf_coil - * tfcoil_variables.n_tf_coil_turns - * tfcoil_variables.a_tf_turn_cable_space_no_void - * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void) - * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_copper) - - tfcoil_variables.len_tf_coil * tfcoil_variables.a_tf_wp_coolant_channels - ) * tfcoil_variables.dcond[ - tfcoil_variables.i_tf_sc_mat - 1 - ] # a_tf_wp_coolant_channels is 0 for a stellarator. but keep this term for now. - # [kg] mass of Copper in conductor - tfcoil_variables.m_tf_coil_copper = ( - tfcoil_variables.len_tf_coil - * tfcoil_variables.n_tf_coil_turns - * tfcoil_variables.a_tf_turn_cable_space_no_void - * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void) - * tfcoil_variables.f_a_tf_turn_cable_copper - - tfcoil_variables.len_tf_coil * tfcoil_variables.a_tf_wp_coolant_channels - ) * constants.den_copper - # [kg] mass of Steel conduit (sheath) - tfcoil_variables.m_tf_wp_steel_conduit = ( - tfcoil_variables.len_tf_coil - * tfcoil_variables.n_tf_coil_turns - * tfcoil_variables.a_tf_turn_steel - * fwbs_variables.den_steel - ) - # if (i_tf_sc_mat==6) tfcoil_variables.m_tf_wp_steel_conduit = fcondsteel * a_tf_wp_no_insulation *tfcoil_variables.len_tf_coil* fwbs_variables.den_steel - # Conduit insulation mass [kg] - # (tfcoil_variables.a_tf_coil_wp_turn_insulation already contains tfcoil_variables.n_tf_coil_turns) - tfcoil_variables.m_tf_coil_wp_turn_insulation = ( - tfcoil_variables.len_tf_coil - * tfcoil_variables.a_tf_coil_wp_turn_insulation - * tfcoil_variables.den_tf_wp_turn_insulation - ) - # [kg] Total conductor mass - tfcoil_variables.m_tf_coil_conductor = ( - tfcoil_variables.m_tf_coil_superconductor - + tfcoil_variables.m_tf_coil_copper - + tfcoil_variables.m_tf_wp_steel_conduit - + tfcoil_variables.m_tf_coil_wp_turn_insulation - ) - # [kg] Total coil mass - tfcoil_variables.m_tf_coils_total = ( - tfcoil_variables.m_tf_coil_case - + tfcoil_variables.m_tf_coil_conductor - + tfcoil_variables.m_tf_coil_wp_insulation - ) * tfcoil_variables.n_tf_coils - # End of general coil geometry values - ####################################################################################### - - ####################################################################################### - # Quench protection: - # - # This copied from the tokamak module: - # Radial position of vacuum vessel [m] - radvv = ( - physics_variables.rmajor - - physics_variables.rminor - - build_variables.dr_fw_plasma_gap_inboard - - build_variables.dr_fw_inboard - - build_variables.dr_blkt_inboard - - build_variables.dr_shld_blkt_gap - - build_variables.dr_shld_inboard - ) - - # Actual VV force density - # Based on reference values from W-7X: - # Bref = 3; - # Iref = 1.3*50; - # aref = 0.92; - # \[Tau]ref = 1.; - # Rref = 5.2; - # dref = 14*10^-3; - - # NOTE: original implementation used taucq which used a EUROfusion - # constant in the calculation. This was the minimum allowed quench time. - # Replacing with the actual quench time. - # MN/m^3 - f_vv_actual = ( - 2.54e6 - * (3e0 * 1.3e0 * 50e0 * 0.92e0**2e0) - / (1e0 * 5.2e0 * 0.014e0) - * ( - physics_variables.b_plasma_toroidal_on_axis - * tfcoil_variables.c_tf_total - * physics_variables.rminor**2 - / ( - (build_variables.dr_vv_inboard + build_variables.dr_vv_outboard) - / 2 - * tfcoil_variables.t_tf_superconductor_quench - * radvv - ) - ) - ** (-1) - ) - - # N/m^2 - # is the vv width the correct length to multiply by to turn the - # force density into a stress? - superconducting_tf_coil_variables.vv_stress_quench = ( - f_vv_actual - * 1e6 - * ((build_variables.dr_vv_inboard + build_variables.dr_vv_outboard) / 2) - ) - - # the conductor fraction is meant of the cable space# - - vd = self.u_max_protect_v( - tfcoil_variables.e_tf_magnetic_stored_total_gj - / tfcoil_variables.n_tf_coils - * 1.0e9, - tfcoil_variables.t_tf_superconductor_quench, - tfcoil_variables.c_tf_turn, - ) - - # comparison - # the new quench protection routine, see #1047 - tfcoil_variables.j_tf_wp_quench_heat_max = self.j_max_protect_am2( - tfcoil_variables.t_tf_superconductor_quench, - 0.0e0, - tfcoil_variables.f_a_tf_turn_cable_copper, - 1 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void, - tfcoil_variables.tftmp, - tfcoil_variables.a_tf_turn_cable_space_no_void, - tfcoil_variables.dx_tf_turn_general**2, - ) - - # print *, "Jmax, comparison: ", j_tf_wp_quench_heat_max, " ", jwdgpro2," ",j_tf_wp/j_tf_wp_quench_heat_max, " , tfcoil_variables.t_tf_superconductor_quench: ",t_tf_superconductor_quench, " tfcoil_variables.f_a_tf_turn_cable_copper: ",f_a_tf_turn_cable_copper - # print *, "a_tf_turn_cable_space_no_void: ", tfcoil_variables.a_tf_turn_cable_space_no_void - # Also give the copper area for REBCO quench calculations: - rebco_variables.coppera_m2 = ( - coilcurrent - * 1.0e6 - / ( - tfcoil_variables.a_tf_wp_conductor - * tfcoil_variables.f_a_tf_turn_cable_copper - ) - ) - tfcoil_variables.v_tf_coil_dump_quench_kv = vd / 1.0e3 # Dump voltage - # - ####################################################################################### - - # Forces scaling # - tfcoil_variables.max_force_density = ( - stellarator_configuration.stella_config_max_force_density - * stellarator_variables.f_i - / stellarator_variables.f_n - * tfcoil_variables.b_tf_inboard_peak_symmetric - / stellarator_configuration.stella_config_wp_bmax - * stellarator_configuration.stella_config_wp_area - / a_tf_wp_no_insulation - ) - - # Approximate, very simple maxiumum stress: (needed for limitation of icc 32) - tfcoil_variables.sig_tf_wp = ( - tfcoil_variables.max_force_density - * tfcoil_variables.dr_tf_wp_with_insulation - * 1.0e6 - ) # in Pa - - # Units: MN/m - max_force_density_mnm = ( - stellarator_configuration.stella_config_max_force_density_mnm - * stellarator_variables.f_i - / stellarator_variables.f_n - * tfcoil_variables.b_tf_inboard_peak_symmetric - / stellarator_configuration.stella_config_wp_bmax - ) - # - max_lateral_force_density = ( - stellarator_configuration.stella_config_max_lateral_force_density - * stellarator_variables.f_i - / stellarator_variables.f_n - * tfcoil_variables.b_tf_inboard_peak_symmetric - / stellarator_configuration.stella_config_wp_bmax - * stellarator_configuration.stella_config_wp_area - / a_tf_wp_no_insulation - ) - max_radial_force_density = ( - stellarator_configuration.stella_config_max_radial_force_density - * stellarator_variables.f_i - / stellarator_variables.f_n - * tfcoil_variables.b_tf_inboard_peak_symmetric - / stellarator_configuration.stella_config_wp_bmax - * stellarator_configuration.stella_config_wp_area - / a_tf_wp_no_insulation - ) - # - # F = f*V = B*j*V \propto B/B0 * I/I0 * A0/A * A/A0 * len/len0 - centering_force_max_mn = ( - stellarator_configuration.stella_config_centering_force_max_mn - * stellarator_variables.f_i - / stellarator_variables.f_n - * tfcoil_variables.b_tf_inboard_peak_symmetric - / stellarator_configuration.stella_config_wp_bmax - * stellarator_configuration.stella_config_coillength - / tfcoil_variables.n_tf_coils - / tfcoil_variables.len_tf_coil - ) - centering_force_min_mn = ( - stellarator_configuration.stella_config_centering_force_min_mn - * stellarator_variables.f_i - / stellarator_variables.f_n - * tfcoil_variables.b_tf_inboard_peak_symmetric - / stellarator_configuration.stella_config_wp_bmax - * stellarator_configuration.stella_config_coillength - / tfcoil_variables.n_tf_coils - / tfcoil_variables.len_tf_coil - ) - centering_force_avg_mn = ( - stellarator_configuration.stella_config_centering_force_avg_mn - * stellarator_variables.f_i - / stellarator_variables.f_n - * tfcoil_variables.b_tf_inboard_peak_symmetric - / stellarator_configuration.stella_config_wp_bmax - * stellarator_configuration.stella_config_coillength - / tfcoil_variables.n_tf_coils - / tfcoil_variables.len_tf_coil - ) - # - #################################### - - if output: - self.stcoil_output( - a_tf_wp_no_insulation, - centering_force_avg_mn, - centering_force_max_mn, - centering_force_min_mn, - coilcoilgap, - rebco_variables.coppera_m2, - rebco_variables.coppera_m2_max, - f_scu, - f_vv_actual, - inductance, - tfcoil_variables.max_force_density, - max_force_density_mnm, - max_lateral_force_density, - max_radial_force_density, - min_bending_radius, - r_coil_major, - r_coil_minor, - r_tf_inleg_mid, - tfcoil_variables.sig_tf_wp, - tfcoil_variables.dx_tf_turn_general, - tfcoil_variables.t_tf_superconductor_quench, - tf_total_h_width, - tfborev, - tfcoil_variables.toroidalgap, - tfcoil_variables.v_tf_coil_dump_quench_max_kv, - tfcoil_variables.v_tf_coil_dump_quench_kv, - ) - - def u_max_protect_v(self, tfes, tdump, aio): - """tfes : input real : Energy stored in one TF coil (J) - tdump : input real : Dump time (sec) - aio : input real : Operating current (A) - """ - return 2 * tfes / (tdump * aio) - - def j_max_protect_am2(self, tau_quench, t_detect, fcu, fcond, temp, acs, aturn): - temp_k = [4, 14, 24, 34, 44, 54, 64, 74, 84, 94, 104, 114, 124] - q_cu_array_sa2m4 = [ - 1.08514e17, - 1.12043e17, - 1.12406e17, - 1.05940e17, - 9.49741e16, - 8.43757e16, - 7.56346e16, - 6.85924e16, - 6.28575e16, - 5.81004e16, - 5.40838e16, - 5.06414e16, - 4.76531e16, - ] - q_he_array_sa2m4 = [ - 3.44562e16, - 9.92398e15, - 4.90462e15, - 2.41524e15, - 1.26368e15, - 7.51617e14, - 5.01632e14, - 3.63641e14, - 2.79164e14, - 2.23193e14, - 1.83832e14, - 1.54863e14, - 1.32773e14, - ] - - q_he = np.interp(temp, temp_k, q_he_array_sa2m4) - q_cu = np.interp(temp, temp_k, q_cu_array_sa2m4) - - # This leaves out the contribution from the superconductor fraction for now - return (acs / aturn) * np.sqrt( - 1 - / (0.5 * tau_quench + t_detect) - * (fcu**2 * fcond**2 * q_cu + fcu * fcond * (1 - fcond) * q_he) - ) - - def jcrit_frommaterial( - self, - bmax, - thelium, - i_tf_sc_mat, - b_crit_upper_nbti, - bcritsc, - f_a_tf_turn_cable_copper, - fhts, - t_crit_nbti, - tcritsc, - f_a_tf_turn_cable_space_extra_void, - jwp, - ): - strain = -0.005 # for now a small value - fhe = f_a_tf_turn_cable_space_extra_void # this is helium fraction in the superconductor (set it to the fixed global variable here) - - fcu = f_a_tf_turn_cable_copper # f_a_tf_turn_cable_copper is a global variable. Is the copper fraction - # of a cable conductor. - - if i_tf_sc_mat == 1: # ITER Nb3Sn critical surface parameterization - bc20m = 32.97 # these are values taken from sctfcoil.f90 - tc0m = 16.06 - - # j_crit_sc returned by itersc is the critical current density in the - # superconductor - not the whole strand, which contains copper - if bmax > bc20m: - j_crit_sc = 1.0e-9 # Set to a small nonzero value - else: - ( - j_crit_sc, - _bcrit, - _tcrit, - ) = superconductors.itersc(thelium, bmax, strain, bc20m, tc0m) - - # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable - j_crit_cable = j_crit_sc * (1.0 - fcu) * (1.0e0 - fhe) - - # This is needed right now. Can we change it later? - j_crit_sc = max(1.0e-9, j_crit_sc) - j_crit_cable = max(1.0e-9, j_crit_cable) - - elif i_tf_sc_mat == 2: - # Bi-2212 high temperature superconductor parameterization - # Current density in a strand of Bi-2212 conductor - # N.B. jcrit returned by bi2212 is the critical current density - # in the strand, not just the superconducting portion. - # The parameterization for j_crit_cable assumes a particular strand - # composition that does not require a user-defined copper fraction, - # so this is irrelevant in this model - - jstrand = jwp / (1 - fhe) - # jstrand = 0 # as far as I can tell this will always be 0 - # because jwp was never set in fortran (so 0) - - j_crit_cable, _tmarg = superconductors.bi2212( - bmax, jstrand, thelium, fhts - ) # bi2212 outputs j_crit_cable - j_crit_sc = j_crit_cable / (1 - fcu) - elif i_tf_sc_mat == 3: # NbTi data - bc20m = 15.0 - tc0m = 9.3 - c0 = 1.0 - - if bmax > bc20m: - j_crit_sc = 1.0e-9 # Set to a small nonzero value - else: - j_crit_sc, _tcrit = superconductors.jcrit_nbti( - thelium, - bmax, - c0, - bc20m, - tc0m, - ) - - # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable - j_crit_cable = j_crit_sc * (1 - fcu) * (1 - fhe) - - # This is needed right now. Can we change it later? - j_crit_sc = max(1.0e-9, j_crit_sc) - j_crit_cable = max(1.0e-9, j_crit_cable) - elif i_tf_sc_mat == 4: # As (1), but user-defined parameters - bc20m = bcritsc - tc0m = tcritsc - j_crit_sc, _bcrit, _tcrit = superconductors.itersc( - thelium, bmax, strain, bc20m, tc0m - ) - # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable - j_crit_cable = j_crit_sc * (1 - fcu) * (1 - fhe) - elif i_tf_sc_mat == 5: # WST Nb3Sn parameterisation - bc20m = 32.97 - tc0m = 16.06 - - # j_crit_sc returned by itersc is the critical current density in the - # superconductor - not the whole strand, which contains copper - - j_crit_sc, _bcrit, _tcrit = superconductors.western_superconducting_nb3sn( - thelium, - bmax, - strain, - bc20m, - tc0m, - ) - # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable - j_crit_cable = j_crit_sc * (1 - fcu) * (1 - fhe) - elif ( - i_tf_sc_mat == 6 - ): # ! "REBCO" 2nd generation HTS superconductor in CrCo strand - j_crit_sc, _validity = superconductors.jcrit_rebco(thelium, bmax, 0) - j_crit_sc = max(1.0e-9, j_crit_sc) - # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable - j_crit_cable = j_crit_sc * (1 - fcu) * (1 - fhe) - - elif i_tf_sc_mat == 7: # Durham Ginzburg-Landau Nb-Ti parameterisation - bc20m = b_crit_upper_nbti - tc0m = t_crit_nbti - j_crit_sc, _bcrit, _tcrit = superconductors.gl_nbti( - thelium, bmax, strain, bc20m, tc0m - ) - # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable - j_crit_cable = j_crit_sc * (1 - fcu) * (1 - fhe) - elif i_tf_sc_mat == 8: - bc20m = 429 - tc0m = 185 - j_crit_sc, _bcrit, _tcrit = superconductors.gl_rebco( - thelium, bmax, strain, bc20m, tc0m - ) - # A0 calculated for tape cross section already - # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable - j_crit_cable = j_crit_sc * (1 - fcu) * (1 - fhe) - else: - raise ProcessValueError( - "Illegal value for i_pf_superconductor", i_tf_sc_mat=i_tf_sc_mat - ) - - return j_crit_sc * 1e-6 - - def bmax_from_awp( - self, wp_width_radial, current, n_tf_coils, r_coil_major, r_coil_minor - ): - """Returns a fitted function for bmax for stellarators - - author: J Lion, IPP Greifswald - Returns a fitted function for bmax in dependece - of the winding pack. The stellarator type config - is taken from the parent scope. - """ - - return ( - 2e-1 - * current - * n_tf_coils - / (r_coil_major - r_coil_minor) - * ( - stellarator_configuration.stella_config_a1 - + stellarator_configuration.stella_config_a2 - * r_coil_major - / wp_width_radial - ) - ) - - def intersect(self, x1, y1, x2, y2, xin): - """Routine to find the x (abscissa) intersection point of two curves - each defined by tabulated (x,y) values - author: P J Knight, CCFE, Culham Science Centre - x1(1:n1) : input real array : x values for first curve - y1(1:n1) : input real array : y values for first curve - n1 : input integer : length of arrays x1, y1 - x2(1:n2) : input real array : x values for first curve - y2(1:n2) : input real array : y values for first curve - n2 : input integer : length of arrays x2, y2 - x : input/output real : initial x value guess on entry; - x value at point of intersection on exit - This routine estimates the x point (abscissa) at which two curves - defined by tabulated (x,y) values intersect, using simple - linear interpolation and the Newton-Raphson method. - The routine will stop with an error message if no crossing point - is found within the x ranges of the two curves. - None - """ - x = xin - n1 = len(x1) - n2 = len(x2) - - xmin = max(np.amin(x1), np.amin(x2)) - xmax = min(np.max(x1), np.amax(x2)) - - if xmin >= xmax: - logger.error( - f"X ranges not overlapping. {np.amin(x1)=} {np.amin(x2)=} " - f"{np.amax(x1)=} {np.amax(x2)=}" - ) - - # Ensure input guess for x is within this range - - if x < xmin: - x = xmin - elif x > xmax: - x = xmax - - # Find overall y range, and set tolerance - # in final difference in y values - - ymin = min(np.amin(y1), np.amin(y2)) - ymax = max(np.max(y1), np.max(y2)) - - epsy = 1.0e-6 * (ymax - ymin) - - # Finite difference dx - - dx = 0.01e0 / max(n1, n2) * (xmax - xmin) - - for _i in range(100): - # Find difference in y values at x - - y01 = np.interp(x, x1, y1) - y02 = np.interp(x, x2, y2) - y = y01 - y02 - - if abs(y) < epsy: - break - - # Find difference in y values at x+dx - - y01 = np.interp(x + dx, x1, y1) - y02 = np.interp(x + dx, x2, y2) - yright = y01 - y02 - - # Find difference in y values at x-dx - - y01 = np.interp(x - dx, x1, y1) - y02 = np.interp(x - dx, x2, y2) - yleft = y01 - y02 - - # Adjust x using Newton-Raphson method - - x = x - 2.0e0 * dx * y / (yright - yleft) - - if x < xmin: - logger.error( - f"X has dropped below Xmin; X={x} has been set equal to Xmin={xmin}" - ) - x = xmin - break - - if x > xmax: - logger.error( - f"X has risen above Xmax; X={x} has been set equal to Xmax={xmin}" - ) - x = xmax - break - else: - logger.error("Convergence too slow; X may be wrong...") - - return x - - def stopt_output( - self, - max_gyrotron_frequency, - b_plasma_toroidal_on_axis, - bt_ecrh, - ne0_max_ECRH, - te0_ecrh_achievable, - ): - po.oheadr(self.outfile, "ECRH Ignition at lower values. Information:") - - po.ovarre( - self.outfile, - "Maximal available gyrotron freq (input)", - "(max_gyro_frequency)", - max_gyrotron_frequency, - ) - - po.ovarre( - self.outfile, - "Operating point: bfield", - "(b_plasma_toroidal_on_axis)", - b_plasma_toroidal_on_axis, - ) - po.ovarre( - self.outfile, - "Operating point: Peak density", - "(nd_plasma_electron_on_axis)", - physics_variables.nd_plasma_electron_on_axis, - ) - po.ovarre( - self.outfile, - "Operating point: Peak temperature", - "(temp_plasma_electron_on_axis_kev)", - physics_variables.temp_plasma_electron_on_axis_kev, - ) - - po.ovarre(self.outfile, "Ignition point: bfield (T)", "(bt_ecrh)", bt_ecrh) - po.ovarre( - self.outfile, - "Ignition point: density (/m3)", - "(ne0_max_ECRH)", - ne0_max_ECRH, - ) - po.ovarre( - self.outfile, - "Maximum reachable ECRH temperature (pseudo) (KEV)", - "(te0_ecrh_achievable)", - te0_ecrh_achievable, - ) - - powerht_local, pscalingmw_local = self.power_at_ignition_point( - max_gyrotron_frequency, te0_ecrh_achievable - ) - po.ovarre( - self.outfile, - "Ignition point: Heating Power (MW)", - "(powerht_ecrh)", - powerht_local, - ) - po.ovarre( - self.outfile, - "Ignition point: Loss Power (MW)", - "(pscalingmw_ecrh)", - pscalingmw_local, - ) - - if powerht_local >= pscalingmw_local: - po.ovarin(self.outfile, "Operation point ECRH ignitable?", "(ecrh_bool)", 1) - else: - po.ovarin(self.outfile, "Operation point ECRH ignitable?", "(ecrh_bool)", 0) - - def power_at_ignition_point(self, gyro_frequency_max, te0_available): - """Routine to calculate if the plasma is ignitable with the current values for the B field. Assumes - current ECRH achievable peak temperature (which is inaccurate as the cordey pass should be calculated) - author: J Lion, IPP Greifswald - gyro_frequency_max : input real : Maximal available Gyrotron frequency (1/s) NOT (rad/s) - te0_available : input real : Reachable peak electron temperature, reached by ECRH (KEV) - powerht_out : output real: Heating Power at ignition point (MW) - pscalingmw_out : output real: Heating Power loss at ignition point (MW) - This routine calculates the density limit due to an ECRH heating scheme on axis - Assumes current peak temperature (which is inaccurate as the cordey pass should be calculated) - Maybe use this: https://doi.org/10.1088/0029-5515/49/8/085026 - """ - te_old = copy(physics_variables.temp_plasma_electron_vol_avg_kev) - # Volume averaged physics_variables.te from te0_achievable - physics_variables.temp_plasma_electron_vol_avg_kev = te0_available / ( - 1.0e0 + physics_variables.alphat - ) - ne0_max, bt_ecrh_max = self.stdlim_ecrh( - gyro_frequency_max, physics_variables.b_plasma_toroidal_on_axis - ) - # Now go to point where ECRH is still available - # In density.. - dene_old = copy(physics_variables.nd_plasma_electrons_vol_avg) - physics_variables.nd_plasma_electrons_vol_avg = min( - dene_old, ne0_max / (1.0e0 + physics_variables.alphan) - ) - - # And B-field.. - bt_old = copy(physics_variables.b_plasma_toroidal_on_axis) - physics_variables.b_plasma_toroidal_on_axis = min( - bt_ecrh_max, physics_variables.b_plasma_toroidal_on_axis - ) - - self.stphys(False) - self.stphys( - False - ) # The second call seems to be necessary for all values to "converge" (and is sufficient) - - powerht_out = max( - copy(physics_variables.p_plasma_loss_mw), 0.00001e0 - ) # the radiation module sometimes returns negative heating power - pscalingmw_out = copy(physics_variables.pscalingmw) - - # Reverse it and do it again because anything more efficiently isn't suitable with the current implementation - # This is bad practice but seems to be necessary as of now: - physics_variables.temp_plasma_electron_vol_avg_kev = te_old - physics_variables.nd_plasma_electrons_vol_avg = dene_old - physics_variables.b_plasma_toroidal_on_axis = bt_old - - self.stphys(False) - self.stphys(False) - - return powerht_out, pscalingmw_out - - def stdlim(self, b_plasma_toroidal_on_axis, powht, rmajor, rminor): - """Routine to calculate the Sudo density limit in a stellarator - author: P J Knight, CCFE, Culham Science Centre - b_plasma_toroidal_on_axis : input real : Toroidal field on axis (T) - powht : input real : Absorbed heating power (MW) - rmajor : input real : Plasma major radius (m) - rminor : input real : Plasma minor radius (m) - nd_plasma_electron_max_array : output real : Maximum volume-averaged plasma density (/m3) - This routine calculates the density limit for a stellarator. - S.Sudo, Y.Takeiri, H.Zushi et al., Scalings of Energy Confinement - and Density Limit in Stellarator/Heliotron Devices, Nuclear Fusion - vol.30, 11 (1990). - """ - arg = powht * b_plasma_toroidal_on_axis / (rmajor * rminor * rminor) - - if arg <= 0.0e0: - raise ProcessValueError( - "Negative square root imminent", - arg=arg, - powht=powht, - b_plasma_toroidal_on_axis=b_plasma_toroidal_on_axis, - rmajor=rmajor, - rminor=rminor, - ) - - # Maximum line-averaged electron density - - dnlamx = 0.25e20 * np.sqrt(arg) - - # Scale the result so that it applies to the volume-averaged - # electron density - - nd_plasma_electron_max_array = ( - dnlamx - * physics_variables.nd_plasma_electrons_vol_avg - / physics_variables.nd_plasma_electron_line - ) - - # Set the required value for icc=5 - - physics_variables.nd_plasma_electrons_max = nd_plasma_electron_max_array - - return nd_plasma_electron_max_array - - def stcoil_output( - self, - a_tf_wp_no_insulation, - centering_force_avg_mn, - centering_force_max_mn, - centering_force_min_mn, - coilcoilgap, - coppera_m2, - coppera_m2_max, - f_scu, - f_vv_actual, - inductance, - max_force_density, - max_force_density_mnm, - max_lateral_force_density, - max_radial_force_density, - min_bending_radius, - r_coil_major, - r_coil_minor, - r_tf_inleg_mid, - sig_tf_wp, - dx_tf_turn_general, - t_tf_superconductor_quench, - tf_total_h_width, - tfborev, - toroidalgap, - v_tf_coil_dump_quench_max_kv, - v_tf_coil_dump_quench_kv, - ): - """Writes stellarator modular coil output to file - author: P J Knight, CCFE, Culham Science Centre - outfile : input integer : output file unit - This routine writes the stellarator modular coil results - to the output file. - None - """ - po.oheadr(self.outfile, "Modular Coils") - - po.osubhd(self.outfile, "General Coil Parameters :") - - po.ovarre( - self.outfile, - "Number of modular coils", - "(n_tf_coils)", - tfcoil_variables.n_tf_coils, - ) - po.ovarre(self.outfile, "Av. coil major radius", "(coil_r)", r_coil_major) - po.ovarre(self.outfile, "Av. coil minor radius", "(coil_a)", r_coil_minor) - po.ovarre( - self.outfile, - "Av. coil aspect ratio", - "(coil_aspect)", - r_coil_major / r_coil_minor, - ) - - po.ovarre( - self.outfile, - "Cross-sectional area per coil (m2)", - "(tfarea/n_tf_coils)", - tfcoil_variables.a_tf_inboard_total / tfcoil_variables.n_tf_coils, - ) - po.ovarre( - self.outfile, - "Total inboard leg radial thickness (m)", - "(dr_tf_inboard)", - build_variables.dr_tf_inboard, - ) - po.ovarre( - self.outfile, - "Total outboard leg radial thickness (m)", - "(dr_tf_outboard)", - build_variables.dr_tf_outboard, - ) - po.ovarre( - self.outfile, - "Inboard leg outboard half-width (m)", - "(tficrn)", - tfcoil_variables.tficrn, - ) - po.ovarre( - self.outfile, - "Inboard leg inboard half-width (m)", - "(tfocrn)", - tfcoil_variables.tfocrn, - ) - po.ovarre( - self.outfile, - "Outboard leg toroidal thickness (m)", - "(dx_tf_inboard_out_toroidal)", - tfcoil_variables.dx_tf_inboard_out_toroidal, - ) - po.ovarre( - self.outfile, "Minimum coil distance (m)", "(toroidalgap)", toroidalgap - ) - po.ovarre( - self.outfile, - "Minimal left gap between coils (m)", - "(coilcoilgap)", - coilcoilgap, - ) - po.ovarre( - self.outfile, - "Minimum coil bending radius (m)", - "(min_bend_radius)", - min_bending_radius, - ) - po.ovarre( - self.outfile, - "Mean coil circumference (m)", - "(len_tf_coil)", - tfcoil_variables.len_tf_coil, - ) - po.ovarre( - self.outfile, - "Total current (MA)", - "(c_tf_total)", - 1.0e-6 * tfcoil_variables.c_tf_total, - ) - po.ovarre( - self.outfile, - "Current per coil(MA)", - "(c_tf_total/n_tf_coils)", - 1.0e-6 * tfcoil_variables.c_tf_total / tfcoil_variables.n_tf_coils, - ) - po.ovarre( - self.outfile, - "Winding pack current density (A/m2)", - "(j_tf_wp)", - tfcoil_variables.j_tf_wp, - ) - po.ovarre( - self.outfile, - "Max allowable current density as restricted by quench (A/m2)", - "(j_tf_wp_quench_heat_max)", - tfcoil_variables.j_tf_wp_quench_heat_max, - ) - po.ovarre( - self.outfile, - "Overall current density (A/m2)", - "(oacdcp)", - tfcoil_variables.oacdcp, - ) - po.ovarre( - self.outfile, - "Maximum field on superconductor (T)", - "(b_tf_inboard_peak_symmetric)", - tfcoil_variables.b_tf_inboard_peak_symmetric, - ) - po.ovarre( - self.outfile, - "Total Stored energy (GJ)", - "(e_tf_magnetic_stored_total_gj)", - tfcoil_variables.e_tf_magnetic_stored_total_gj, - ) - po.ovarre(self.outfile, "Inductance of TF Coils (H)", "(inductance)", inductance) - po.ovarre( - self.outfile, - "Total mass of coils (kg)", - "(m_tf_coils_total)", - tfcoil_variables.m_tf_coils_total, - ) - - po.osubhd(self.outfile, "Coil Geometry :") - po.ovarre( - self.outfile, - "Inboard leg centre radius (m)", - "(r_tf_inleg_mid)", - r_tf_inleg_mid, - ) - po.ovarre( - self.outfile, - "Outboard leg centre radius (m)", - "(r_tf_outboard_mid)", - build_variables.r_tf_outboard_mid, - ) - po.ovarre( - self.outfile, - "Maximum inboard edge height (m)", - "(z_tf_inside_half)", - build_variables.z_tf_inside_half, - ) - po.ovarre( - self.outfile, - "Clear horizontal dr_bore (m)", - "(tf_total_h_width)", - tf_total_h_width, - ) - po.ovarre(self.outfile, "Clear vertical dr_bore (m)", "(tfborev)", tfborev) - - po.osubhd(self.outfile, "Conductor Information :") - po.ovarre( - self.outfile, - "Superconductor mass per coil (kg)", - "(m_tf_coil_superconductor)", - tfcoil_variables.m_tf_coil_superconductor, - ) - po.ovarre( - self.outfile, - "Copper mass per coil (kg)", - "(m_tf_coil_copper)", - tfcoil_variables.m_tf_coil_copper, - ) - po.ovarre( - self.outfile, - "Steel conduit mass per coil (kg)", - "(m_tf_wp_steel_conduit)", - tfcoil_variables.m_tf_wp_steel_conduit, - ) - po.ovarre( - self.outfile, - "Total conductor cable mass per coil (kg)", - "(m_tf_coil_conductor)", - tfcoil_variables.m_tf_coil_conductor, - ) - po.ovarre( - self.outfile, - "Cable conductor + void area (m2)", - "(a_tf_turn_cable_space_no_void)", - tfcoil_variables.a_tf_turn_cable_space_no_void, - ) - po.ovarre( - self.outfile, - "Cable space coolant fraction", - "(f_a_tf_turn_cable_space_extra_void)", - tfcoil_variables.f_a_tf_turn_cable_space_extra_void, - ) - po.ovarre( - self.outfile, - "Conduit case thickness (m)", - "(dx_tf_turn_steel)", - tfcoil_variables.dx_tf_turn_steel, - ) - po.ovarre( - self.outfile, - "Cable insulation thickness (m)", - "(dx_tf_turn_insulation)", - tfcoil_variables.dx_tf_turn_insulation, - ) - - ap = a_tf_wp_no_insulation - po.osubhd(self.outfile, "Winding Pack Information :") - po.ovarre(self.outfile, "Winding pack area", "(ap)", ap) - po.ovarre( - self.outfile, - "Conductor fraction of winding pack", - "(a_tf_wp_conductor/ap)", - tfcoil_variables.a_tf_wp_conductor / ap, - ) - po.ovarre( - self.outfile, - "Copper fraction of conductor", - "(f_a_tf_turn_cable_copper)", - tfcoil_variables.f_a_tf_turn_cable_copper, - ) - po.ovarre( - self.outfile, - "Structure fraction of winding pack", - "(a_tf_wp_steel/ap)", - tfcoil_variables.a_tf_wp_steel / ap, - ) - po.ovarre( - self.outfile, - "Insulator fraction of winding pack", - "(a_tf_coil_wp_turn_insulation/ap)", - tfcoil_variables.a_tf_coil_wp_turn_insulation / ap, - ) - po.ovarre( - self.outfile, - "Helium fraction of winding pack", - "(a_tf_wp_extra_void/ap)", - tfcoil_variables.a_tf_wp_extra_void / ap, - ) - po.ovarre( - self.outfile, - "Winding radial thickness (m)", - "(dr_tf_wp_with_insulation)", - tfcoil_variables.dr_tf_wp_with_insulation, - ) - po.ovarre( - self.outfile, - "Winding toroidal thickness (m)", - "(dx_tf_wp_primary_toroidal)", - tfcoil_variables.dx_tf_wp_primary_toroidal, - ) - po.ovarre( - self.outfile, - "Ground wall insulation thickness (m)", - "(dx_tf_wp_insulation)", - tfcoil_variables.dx_tf_wp_insulation, - ) - po.ovarre( - self.outfile, - "Number of turns per coil", - "(n_tf_coil_turns)", - tfcoil_variables.n_tf_coil_turns, - ) - po.ovarre( - self.outfile, - "Width of each turn (incl. insulation) (m)", - "(dx_tf_turn_general)", - dx_tf_turn_general, - ) - po.ovarre( - self.outfile, - "Current per turn (A)", - "(c_tf_turn)", - tfcoil_variables.c_tf_turn, - ) - po.ovarre( - self.outfile, - "Current density in conductor area (A/m2)", - "(c_tf_total/a_tf_wp_conductor)", - 1.0e-6 - * tfcoil_variables.c_tf_total - / tfcoil_variables.n_tf_coils - / tfcoil_variables.a_tf_wp_conductor, - ) - po.ovarre( - self.outfile, - "Current density in SC area (A/m2)", - "(c_tf_total/a_tf_wp_conductor/f_scu)", - 1.0e-6 - * tfcoil_variables.c_tf_total - / tfcoil_variables.n_tf_coils - / ap - / f_scu, - ) - po.ovarre(self.outfile, "Superconductor faction of WP (1)", "(f_scu)", f_scu) - - po.osubhd(self.outfile, "Forces and Stress :") - po.ovarre( - self.outfile, - "Maximal toroidally and radially av. force density (MN/m3)", - "(max_force_density)", - max_force_density, - ) - po.ovarre( - self.outfile, - "Maximal force density (MN/m)", - "(max_force_density_Mnm)", - max_force_density_mnm, - ) - po.ovarre( - self.outfile, - "Maximal stress (approx.) (MPa)", - "(sig_tf_wp)", - sig_tf_wp * 1.0e-6, - ) - - po.ovarre( - self.outfile, - "Maximal lateral force density (MN/m3)", - "(max_lateral_force_density)", - max_lateral_force_density, - ) - po.ovarre( - self.outfile, - "Maximal radial force density (MN/m3)", - "(max_radial_force_density)", - max_radial_force_density, - ) - - po.ovarre( - self.outfile, - "Max. centering force (coil) (MN)", - "(centering_force_max_MN)", - centering_force_max_mn, - ) - po.ovarre( - self.outfile, - "Min. centering force (coil) (MN)", - "(centering_force_min_MN)", - centering_force_min_mn, - ) - po.ovarre( - self.outfile, - "Avg. centering force per coil (MN)", - "(centering_force_avg_MN)", - centering_force_avg_mn, - ) - - po.osubhd(self.outfile, "Quench Restrictions :") - po.ovarre( - self.outfile, - "Actual quench time (or time constant) (s)", - "(t_tf_superconductor_quench)", - t_tf_superconductor_quench, - ) - po.ovarre( - self.outfile, - "Actual quench vaccuum vessel force density (MN/m^3)", - "(f_vv_actual)", - f_vv_actual, - ) - po.ovarre( - self.outfile, - "Maximum allowed voltage during quench due to insulation (kV)", - "(v_tf_coil_dump_quench_max_kv)", - v_tf_coil_dump_quench_max_kv, - ) - po.ovarre( - self.outfile, - "Actual quench voltage (kV)", - "(v_tf_coil_dump_quench_kv)", - v_tf_coil_dump_quench_kv, - "OP ", - ) - po.ovarre( - self.outfile, - "Current (A) per mm^2 copper (A/mm2)", - "(coppera_m2)", - coppera_m2 * 1.0e-6, - ) - po.ovarre( - self.outfile, - "Max Copper current fraction:", - "(coppera_m2/coppera_m2_max)", - coppera_m2 / coppera_m2_max, - ) - - po.osubhd(self.outfile, "External Case Information :") - - po.ovarre( - self.outfile, - "Case thickness, plasma side (m)", - "(dr_tf_plasma_case)", - tfcoil_variables.dr_tf_plasma_case, - ) - po.ovarre( - self.outfile, - "Case thickness, outer side (m)", - "(dr_tf_nose_case)", - tfcoil_variables.dr_tf_nose_case, - ) - po.ovarre( - self.outfile, - "Case toroidal thickness (m)", - "(dx_tf_side_case_min)", - tfcoil_variables.dx_tf_side_case_min, - ) - po.ovarre( - self.outfile, - "Case area per coil (m2)", - "(a_tf_coil_inboard_case)", - tfcoil_variables.a_tf_coil_inboard_case, - ) - po.ovarre( - self.outfile, - "External case mass per coil (kg)", - "(m_tf_coil_case)", - tfcoil_variables.m_tf_coil_case, - ) - - po.osubhd(self.outfile, "Available Space for Ports :") - - po.ovarre( - self.outfile, - "Max toroidal size of vertical ports (m)", - "(vporttmax)", - stellarator_variables.vporttmax, - ) - po.ovarre( - self.outfile, - "Max poloidal size of vertical ports (m)", - "(vportpmax)", - stellarator_variables.vportpmax, - ) - po.ovarre( - self.outfile, - "Max area of vertical ports (m2)", - "(vportamax)", - stellarator_variables.vportamax, - ) - po.ovarre( - self.outfile, - "Max toroidal size of horizontal ports (m)", - "(hporttmax)", - stellarator_variables.hporttmax, - ) - po.ovarre( - self.outfile, - "Max poloidal size of horizontal ports (m)", - "(hportpmax)", - stellarator_variables.hportpmax, - ) - po.ovarre( - self.outfile, - "Max area of horizontal ports (m2)", - "(hportamax)", - stellarator_variables.hportamax, - ) - - def stdlim_ecrh(self, gyro_frequency_max, bt_input): - """Routine to calculate the density limit due to an ECRH heating scheme on axis - depending on an assumed maximal available gyrotron frequency. - author: J Lion, IPP Greifswald - gyro_frequency_max : input real : Maximal available Gyrotron frequency (1/s) NOT (rad/s) - b_plasma_toroidal_on_axis : input real : Maximal magnetic field on axis (T) - dlimit_ecrh : output real : Maximum peak plasma density by ECRH constraints (/m3) - bt_max : output real : Maximum allowable b field for ecrh heating (T) - This routine calculates the density limit due to an ECRH heating scheme on axis - """ - gyro_frequency = min(1.76e11 * bt_input, gyro_frequency_max * 2.0e0 * np.pi) - - # Restrict b field to the maximal available gyrotron frequency - bt_max = (gyro_frequency_max * 2.0e0 * np.pi) / 1.76e11 - - # me*e0/e^2 * w^2 - ne0_max = max(0.0e0, 3.142077e-4 * gyro_frequency**2) - - # Check if parabolic profiles are used: - if physics_variables.i_plasma_pedestal == 0: - # Parabolic profiles used, use analytical formula: - dlimit_ecrh = ne0_max - else: - logger.error( - "It was used physics_variables.i_plasma_pedestal = 1 in a stellarator routine. PROCESS will pretend it got parabolic profiles (physics_variables.i_plasma_pedestal = 0)." - ) - dlimit_ecrh = ne0_max - - return dlimit_ecrh, bt_max - - def stphys(self, output): - """Routine to calculate stellarator plasma physics information - author: P J Knight, CCFE, Culham Science Centre - author: F Warmer, IPP Greifswald - None - This routine calculates the physics quantities relevant to - a stellarator device. - AEA FUS 172: Physics Assessment for the European Reactor Study - """ - # ############################################### - # Calculate plasma composition - # Issue #261 Remove old radiation model - - self.physics.plasma_composition() - - # Calculate density and temperature profile quantities - self.plasma_profile.run() - - # Total field - physics_variables.b_plasma_total = np.sqrt( - physics_variables.b_plasma_toroidal_on_axis**2 - + physics_variables.b_plasma_poloidal_average**2 - ) - - # Check if physics_variables.beta (iteration variable 5) is an iteration variable - if 5 in numerics.ixc: - raise ProcessValueError( - "Beta should not be in ixc if istell>0. Use Constraints 24 and 84 instead" - ) - - # Set physics_variables.beta as a consequence: - # This replaces constraint equation 1 as it is just an equality. - physics_variables.beta_total_vol_avg = ( - physics_variables.beta_fast_alpha - + physics_variables.beta_beam - + 2.0e3 - * constants.RMU0 - * constants.ELECTRON_CHARGE - * ( - physics_variables.nd_plasma_electrons_vol_avg - * physics_variables.temp_plasma_electron_density_weighted_kev - + physics_variables.nd_plasma_ions_total_vol_avg - * physics_variables.temp_plasma_ion_density_weighted_kev - ) - / physics_variables.b_plasma_total**2 - ) - physics_variables.e_plasma_beta = ( - 1.5e0 - * physics_variables.beta_total_vol_avg - * physics_variables.b_plasma_total - * physics_variables.b_plasma_total - / (2.0e0 * constants.RMU0) - * physics_variables.vol_plasma - ) - - physics_variables.rho_star = np.sqrt( - 2.0e0 - * constants.PROTON_MASS - * physics_variables.m_ions_total_amu - * physics_variables.e_plasma_beta - / ( - 3.0e0 - * physics_variables.vol_plasma - * physics_variables.nd_plasma_electron_line - ) - ) / ( - constants.ELECTRON_CHARGE - * physics_variables.b_plasma_toroidal_on_axis - * physics_variables.eps - * physics_variables.rmajor - ) - - # Calculate poloidal field using rotation transform - physics_variables.b_plasma_poloidal_average = ( - physics_variables.rminor - * physics_variables.b_plasma_toroidal_on_axis - / physics_variables.rmajor - * stellarator_variables.iotabar - ) - - # Poloidal physics_variables.beta - - # Perform auxiliary power calculations - - self.stheat(False) - - # Calculate fusion power - - fusion_reactions = reactions.FusionReactionRate(self.plasma_profile) - fusion_reactions.deuterium_branching( - physics_variables.temp_plasma_ion_vol_avg_kev - ) - fusion_reactions.calculate_fusion_rates() - fusion_reactions.set_physics_variables() - - # D-T power density is named differently to differentiate it from the beam given component - physics_variables.p_plasma_dt_mw = ( - physics_variables.dt_power_density_plasma * physics_variables.vol_plasma - ) - physics_variables.p_dhe3_total_mw = ( - physics_variables.dhe3_power_density * physics_variables.vol_plasma - ) - physics_variables.p_dd_total_mw = ( - physics_variables.dd_power_density * physics_variables.vol_plasma - ) - - # Calculate neutral beam slowing down effects - # If ignited, then ignore beam fusion effects - - if (current_drive_variables.p_hcd_beam_injected_total_mw != 0.0e0) and ( - physics_variables.i_plasma_ignited == 0 - ): - ( - physics_variables.beta_beam, - physics_variables.nd_beam_ions_out, - physics_variables.p_beam_alpha_mw, - ) = reactions.beam_fusion( - physics_variables.beamfus0, - physics_variables.betbm0, - physics_variables.b_plasma_poloidal_average, - physics_variables.b_plasma_toroidal_on_axis, - current_drive_variables.c_beam_total, - physics_variables.nd_plasma_electrons_vol_avg, - physics_variables.nd_plasma_fuel_ions_vol_avg, - physics_variables.dlamie, - current_drive_variables.e_beam_kev, - physics_variables.f_plasma_fuel_deuterium, - physics_variables.f_plasma_fuel_tritium, - current_drive_variables.f_beam_tritium, - physics_variables.sigmav_dt_average, - physics_variables.temp_plasma_electron_density_weighted_kev, - physics_variables.temp_plasma_ion_density_weighted_kev, - physics_variables.vol_plasma, - physics_variables.n_charge_plasma_effective_mass_weighted_vol_avg, - ) - physics_variables.fusden_total = ( - physics_variables.fusden_plasma - + 1.0e6 - * physics_variables.p_beam_alpha_mw - / (constants.DT_ALPHA_ENERGY) - / physics_variables.vol_plasma - ) - physics_variables.fusden_alpha_total = ( - physics_variables.fusden_plasma_alpha - + 1.0e6 - * physics_variables.p_beam_alpha_mw - / (constants.DT_ALPHA_ENERGY) - / physics_variables.vol_plasma - ) - physics_variables.p_dt_total_mw = ( - physics_variables.p_plasma_dt_mw - + 5.0e0 * physics_variables.p_beam_alpha_mw - ) - else: - # If no beams present then the total alpha rates and power are the same as the plasma values - physics_variables.fusden_total = physics_variables.fusden_plasma - physics_variables.fusden_alpha_total = physics_variables.fusden_plasma_alpha - physics_variables.p_dt_total_mw = physics_variables.p_plasma_dt_mw - - # Create some derived values and add beam contribution to fusion power - ( - physics_variables.pden_neutron_total_mw, - physics_variables.p_plasma_alpha_mw, - physics_variables.p_alpha_total_mw, - physics_variables.p_plasma_neutron_mw, - physics_variables.p_neutron_total_mw, - physics_variables.p_non_alpha_charged_mw, - physics_variables.pden_alpha_total_mw, - physics_variables.f_pden_alpha_electron_mw, - physics_variables.f_pden_alpha_ions_mw, - physics_variables.p_charged_particle_mw, - physics_variables.p_fusion_total_mw, - ) = reactions.set_fusion_powers( - physics_variables.f_alpha_electron, - physics_variables.f_alpha_ion, - physics_variables.p_beam_alpha_mw, - physics_variables.pden_non_alpha_charged_mw, - physics_variables.pden_plasma_neutron_mw, - physics_variables.vol_plasma, - physics_variables.pden_plasma_alpha_mw, - ) - - physics_variables.beta_fast_alpha = physics_funcs.fast_alpha_beta( - physics_variables.b_plasma_poloidal_average, - physics_variables.b_plasma_toroidal_on_axis, - physics_variables.nd_plasma_electrons_vol_avg, - physics_variables.nd_plasma_fuel_ions_vol_avg, - physics_variables.nd_plasma_ions_total_vol_avg, - physics_variables.temp_plasma_electron_density_weighted_kev, - physics_variables.temp_plasma_ion_density_weighted_kev, - physics_variables.pden_alpha_total_mw, - physics_variables.pden_plasma_alpha_mw, - physics_variables.i_beta_fast_alpha, - ) - - # Neutron wall load - - if physics_variables.i_pflux_fw_neutron == 1: - physics_variables.pflux_fw_neutron_mw = ( - physics_variables.ffwal - * physics_variables.p_neutron_total_mw - / physics_variables.a_plasma_surface - ) - else: - if heat_transport_variables.ipowerflow == 0: - physics_variables.pflux_fw_neutron_mw = ( - (1.0e0 - fwbs_variables.fhole) - * physics_variables.p_neutron_total_mw - / build_variables.a_fw_total - ) - else: - physics_variables.pflux_fw_neutron_mw = ( - ( - 1.0e0 - - fwbs_variables.fhole - - fwbs_variables.f_a_fw_outboard_hcd - - fwbs_variables.f_ster_div_single - ) - * physics_variables.p_neutron_total_mw - / build_variables.a_fw_total - ) - - # Calculate ion/electron equilibration power - - physics_variables.pden_ion_electron_equilibration_mw = rether( - physics_variables.alphan, - physics_variables.alphat, - physics_variables.nd_plasma_electrons_vol_avg, - physics_variables.dlamie, - physics_variables.temp_plasma_electron_vol_avg_kev, - physics_variables.temp_plasma_ion_vol_avg_kev, - physics_variables.n_charge_plasma_effective_mass_weighted_vol_avg, - ) - - # Calculate radiation power - radpwr_data = physics_funcs.calculate_radiation_powers( - self.plasma_profile, - physics_variables.nd_plasma_electron_on_axis, - physics_variables.rminor, - physics_variables.b_plasma_toroidal_on_axis, - physics_variables.aspect, - physics_variables.alphan, - physics_variables.alphat, - physics_variables.tbeta, - physics_variables.temp_plasma_electron_on_axis_kev, - physics_variables.f_sync_reflect, - physics_variables.rmajor, - physics_variables.kappa, - physics_variables.vol_plasma, - ) - physics_variables.pden_plasma_sync_mw = radpwr_data.pden_plasma_sync_mw - physics_variables.pden_plasma_core_rad_mw = radpwr_data.pden_plasma_core_rad_mw - physics_variables.pden_plasma_outer_rad_mw = radpwr_data.pden_plasma_outer_rad_mw - physics_variables.pden_plasma_rad_mw = radpwr_data.pden_plasma_rad_mw - - physics_variables.pden_plasma_core_rad_mw = max( - physics_variables.pden_plasma_core_rad_mw, 0.0e0 - ) - physics_variables.pden_plasma_outer_rad_mw = max( - physics_variables.pden_plasma_outer_rad_mw, 0.0e0 - ) - - physics_variables.p_plasma_inner_rad_mw = ( - physics_variables.pden_plasma_core_rad_mw * physics_variables.vol_plasma - ) # Should probably be vol_core - physics_variables.p_plasma_outer_rad_mw = ( - physics_variables.pden_plasma_outer_rad_mw * physics_variables.vol_plasma - ) - - physics_variables.p_plasma_rad_mw = ( - physics_variables.pden_plasma_rad_mw * physics_variables.vol_plasma - ) - - # Heating power to plasma (= Psol in divertor model) - # Ohmic power is zero in a stellarator - # physics_variables.p_plasma_rad_mw here is core + edge (no SOL) - - powht = ( - physics_variables.f_p_alpha_plasma_deposited - * physics_variables.p_alpha_total_mw - + physics_variables.p_non_alpha_charged_mw - + physics_variables.p_plasma_ohmic_mw - - physics_variables.pden_plasma_rad_mw * physics_variables.vol_plasma - ) - powht = max( - 0.00001e0, powht - ) # To avoid negative heating power. This line is VERY important - - if physics_variables.i_plasma_ignited == 0: - powht = ( - powht + current_drive_variables.p_hcd_injected_total_mw - ) # if not ignited add the auxiliary power - - # Here the implementation sometimes leaves the accessible regime when p_plasma_rad_mw> powht which is unphysical and - # is not taken care of by the rad module. We restrict the radiation power here by the heating power: - physics_variables.p_plasma_rad_mw = max(0.0e0, physics_variables.p_plasma_rad_mw) - - # Power to divertor, = (1-stellarator_variables.f_rad)*Psol - - # The SOL radiation needs to be smaller than the physics_variables.p_plasma_rad_mw - physics_variables.psolradmw = stellarator_variables.f_rad * powht - physics_variables.p_plasma_separatrix_mw = powht - physics_variables.psolradmw - - # Add SOL Radiation to total - physics_variables.p_plasma_rad_mw = ( - physics_variables.p_plasma_rad_mw + physics_variables.psolradmw - ) - # pden_plasma_rad_mw = physics_variables.p_plasma_rad_mw / physics_variables.vol_plasma # this line OVERWRITES the original definition of pden_plasma_rad_mw, probably shouldn't be defined like that as the core does not lose SOL power. - - # The following line is unphysical, but prevents -ve sqrt argument - # Should be obsolete if constraint eqn 17 is turned on (but beware - - # this may not be quite correct for stellarators) - physics_variables.p_plasma_separatrix_mw = max( - 0.001e0, physics_variables.p_plasma_separatrix_mw - ) - - # Power transported to the first wall by escaped alpha particles - - physics_variables.p_fw_alpha_mw = physics_variables.p_alpha_total_mw * ( - 1.0e0 - physics_variables.f_p_alpha_plasma_deposited - ) - - # Nominal mean photon wall load - if physics_variables.i_pflux_fw_neutron == 1: - physics_variables.pflux_fw_rad_mw = ( - physics_variables.ffwal - * physics_variables.p_plasma_rad_mw - / physics_variables.a_plasma_surface - ) - else: - if heat_transport_variables.ipowerflow == 0: - physics_variables.pflux_fw_rad_mw = ( - (1.0e0 - fwbs_variables.fhole) - * physics_variables.p_plasma_rad_mw - / build_variables.a_fw_total - ) - else: - physics_variables.pflux_fw_rad_mw = ( - ( - 1.0e0 - - fwbs_variables.fhole - - fwbs_variables.f_a_fw_outboard_hcd - - fwbs_variables.f_ster_div_single - ) - * physics_variables.p_plasma_rad_mw - / build_variables.a_fw_total - ) - - constraint_variables.pflux_fw_rad_max_mw = ( - physics_variables.pflux_fw_rad_mw * constraint_variables.f_fw_rad_max - ) - - physics_variables.rad_fraction_total = physics_variables.p_plasma_rad_mw / ( - physics_variables.f_p_alpha_plasma_deposited - * physics_variables.p_alpha_total_mw - + physics_variables.p_non_alpha_charged_mw - + physics_variables.p_plasma_ohmic_mw - + current_drive_variables.p_hcd_injected_total_mw - ) - - # Calculate transport losses and energy confinement time using the - # chosen scaling law - # N.B. stellarator_variables.iotabar replaces tokamak physics_variables.q95 in argument list - - ( - physics_variables.pden_electron_transport_loss_mw, - physics_variables.pden_ion_transport_loss_mw, - physics_variables.t_electron_energy_confinement, - physics_variables.t_ion_energy_confinement, - physics_variables.t_energy_confinement, - physics_variables.p_plasma_loss_mw, - ) = self.physics.calculate_confinement_time( - physics_variables.m_fuel_amu, - physics_variables.p_alpha_total_mw, - physics_variables.aspect, - physics_variables.b_plasma_toroidal_on_axis, - physics_variables.nd_plasma_ions_total_vol_avg, - physics_variables.nd_plasma_electrons_vol_avg, - physics_variables.nd_plasma_electron_line, - physics_variables.eps, - physics_variables.hfact, - physics_variables.i_confinement_time, - physics_variables.i_plasma_ignited, - physics_variables.kappa, - physics_variables.kappa95, - physics_variables.p_non_alpha_charged_mw, - current_drive_variables.p_hcd_injected_total_mw, - physics_variables.plasma_current, - physics_variables.pden_plasma_core_rad_mw, - physics_variables.rmajor, - physics_variables.rminor, - physics_variables.temp_plasma_electron_density_weighted_kev, - physics_variables.temp_plasma_ion_density_weighted_kev, - stellarator_variables.iotabar, - physics_variables.qstar, - physics_variables.vol_plasma, - physics_variables.n_charge_plasma_effective_vol_avg, - ) - - physics_variables.p_electron_transport_loss_mw = ( - physics_variables.pden_electron_transport_loss_mw - * physics_variables.vol_plasma - ) - physics_variables.p_ion_transport_loss_mw = ( - physics_variables.pden_ion_transport_loss_mw * physics_variables.vol_plasma - ) - - physics_variables.pscalingmw = ( - physics_variables.p_electron_transport_loss_mw - + physics_variables.p_ion_transport_loss_mw - ) - - # Calculate auxiliary physics related information - # for the rest of the code - - sbar = 1.0e0 - ( - physics_variables.burnup, - physics_variables.ntau, - physics_variables.nTtau, - physics_variables.figmer, - _fusrat, - physics_variables.molflow_plasma_fuelling_required, - physics_variables.rndfuel, - physics_variables.t_alpha_confinement, - physics_variables.f_alpha_energy_confinement, - ) = self.physics.phyaux( - physics_variables.aspect, - physics_variables.nd_plasma_electrons_vol_avg, - physics_variables.temp_plasma_electron_vol_avg_kev, - physics_variables.nd_plasma_fuel_ions_vol_avg, - physics_variables.fusden_total, - physics_variables.fusden_alpha_total, - physics_variables.plasma_current, - sbar, - physics_variables.nd_plasma_alphas_vol_avg, - physics_variables.t_energy_confinement, - physics_variables.vol_plasma, - ) - - # Calculate physics_variables.beta limit. Does nothing atm so commented out - # call stblim(physics_variables.beta_vol_avg_max) - - # Calculate the neoclassical sanity check with PROCESS parameters - ( - q_PROCESS, - q_PROCESS_r1, - _q_neo, - _gamma_neo, - _total_q_neo, - total_q_neo_e, - q_neo_e, - _q_neo_D, - _q_neo_a, - _q_neo_T, - g_neo_e, - _g_neo_D, - _g_neo_a, - _g_neo_T, - dndt_neo_e, - _dndt_neo_D, - _dndt_neo_a, - _dndt_neo_T, - _dndt_neo_fuel, - _dmdt_neo_fuel, - dmdt_neo_fuel_from_e, - chi_neo_e, - chi_PROCESS_e, - nu_star_e, - nu_star_d, - nu_star_T, - nu_star_He, - ) = self.calc_neoclassics() - - if output: - self.stphys_output( - q_PROCESS, - total_q_neo_e, - dmdt_neo_fuel_from_e, - q_PROCESS_r1, - chi_PROCESS_e, - chi_neo_e, - q_neo_e, - g_neo_e, - dndt_neo_e, - physics_variables.rho_ne_max, - physics_variables.rho_te_max, - physics_variables.gradient_length_ne, - physics_variables.gradient_length_te, - physics_variables.rho_star, - nu_star_e, - nu_star_d, - nu_star_T, - nu_star_He, - physics_variables.nd_plasma_electron_line, - physics_variables.nd_plasma_electrons_max, - ) - - def stphys_output( - self, - q_PROCESS, - total_q_neo_e, - dmdt_neo_fuel_from_e, - q_PROCESS_r1, - chi_PROCESS_e, - chi_neo_e, - q_neo_e, - g_neo_e, - dndt_neo_e, - rho_ne_max, - rho_te_max, - gradient_length_ne, - gradient_length_te, - rho_star, - nu_star_e, - nu_star_D, - nu_star_T, - nu_star_He, - nd_plasma_electron_line, - nd_plasma_electrons_max, - ): - po.oheadr(self.outfile, "Stellarator Specific Physics:") - - po.ovarre( - self.outfile, - "Total 0D heat flux (r=rhocore) (MW/m2)", - "(q_PROCESS)", - q_PROCESS, - ) - po.ovarre( - self.outfile, - "Total neoclassical flux from 4*q_e (r=rhocore) (MW/m2)", - "(total_q_neo_e)", - total_q_neo_e, - ) - - po.ovarre( - self.outfile, - "Total fuel (DT) mass flux by using 4 * neoclassical e transport (mg/s): ", - "(dmdt_neo_fuel_from_e)", - dmdt_neo_fuel_from_e, - ) - po.ovarre( - self.outfile, - "Considered Heatflux by LCFS heat flux ratio (1)", - "(q_PROCESS/q_PROCESS_r1)", - q_PROCESS / q_PROCESS_r1, - ) - - po.ovarre( - self.outfile, - "Resulting electron effective chi (0D) (r=rhocore): ", - "(chi_PROCESS_e)", - chi_PROCESS_e, - ) - po.ovarre( - self.outfile, - "Neoclassical electron effective chi (r=rhocore): ", - "(chi_neo_e)", - chi_neo_e, - ) - - po.ovarre( - self.outfile, - "Heat flux due to neoclassical energy transport (e) (MW/m2): ", - "(q_neo_e)", - q_neo_e, - ) - po.ovarre( - self.outfile, - "Heat flux due to neoclassical particle transport (e) (MW/m2): ", - "(g_neo_e)", - g_neo_e, - ) - po.ovarre( - self.outfile, - "Particle flux due to neoclassical particle transport (e) (1/m2/s): ", - "(dndt_neo_e)", - dndt_neo_e, - ) - - po.ovarre( - self.outfile, "r/a of maximum ne gradient (m)", "(rho_ne_max)", rho_ne_max - ) - po.ovarre( - self.outfile, "r/a of maximum te gradient (m)", "(rho_te_max)", rho_te_max - ) - po.ovarre( - self.outfile, - "Maxium ne gradient length (1)", - "(gradient_length_ne)", - gradient_length_ne, - ) - po.ovarre( - self.outfile, - "Maxium te gradient length (1)", - "(gradient_length_te)", - gradient_length_te, - ) - po.ovarre( - self.outfile, - "Gradient Length Ratio (T/n) (1)", - "(gradient_length_ratio)", - gradient_length_te / gradient_length_ne, - ) - - po.ovarre(self.outfile, "Normalized ion Larmor radius", "(rho_star)", rho_star) - po.ovarre( - self.outfile, - "Normalized collisionality (electrons)", - "(nu_star_e)", - nu_star_e, - ) - po.ovarre( - self.outfile, "Normalized collisionality (D)", "(nu_star_D)", nu_star_D - ) - po.ovarre( - self.outfile, "Normalized collisionality (T)", "(nu_star_T)", nu_star_T - ) - po.ovarre( - self.outfile, "Normalized collisionality (He)", "(nu_star_He)", nu_star_He - ) - - po.ovarre( - self.outfile, - "Obtained line averaged density at op. point (/m3)", - "(nd_plasma_electron_line)", - nd_plasma_electron_line, - ) - po.ovarre( - self.outfile, - "Sudo density limit (/m3)", - "(nd_plasma_electrons_max)", - nd_plasma_electrons_max, - ) - po.ovarre( - self.outfile, - "Ratio density to sudo limit (1)", - "(nd_plasma_electron_line/nd_plasma_electrons_max)", - nd_plasma_electron_line / nd_plasma_electrons_max, - ) - - def calc_neoclassics(self): - self.neoclassics.init_neoclassics( - 0.6, - stellarator_configuration.stella_config_epseff, - stellarator_variables.iotabar, - ) - - q_PROCESS = ( - ( - physics_variables.f_p_alpha_plasma_deposited - * physics_variables.pden_alpha_total_mw - - physics_variables.pden_plasma_core_rad_mw - ) - * physics_variables.vol_plasma - / physics_variables.a_plasma_surface - * impurity_radiation_module.radius_plasma_core_norm - ) - q_PROCESS_r1 = ( - ( - physics_variables.f_p_alpha_plasma_deposited - * physics_variables.pden_alpha_total_mw - - physics_variables.pden_plasma_core_rad_mw - ) - * physics_variables.vol_plasma - / physics_variables.a_plasma_surface - ) - - q_neo = sum(neoclassics_variables.q_flux * 1e-6) - gamma_neo = sum( - neoclassics_variables.gamma_flux * neoclassics_variables.temperatures * 1e-6 - ) - - total_q_neo = sum( - neoclassics_variables.q_flux * 1e-6 - + neoclassics_variables.gamma_flux - * neoclassics_variables.temperatures - * 1e-6 - ) - - total_q_neo_e = ( - 2 - * 2 - * ( - neoclassics_variables.q_flux[0] * 1e-6 - + neoclassics_variables.gamma_flux[0] - * neoclassics_variables.temperatures[0] - * 1e-6 - ) - ) - - q_neo_e = neoclassics_variables.q_flux[0] * 1e-6 - q_neo_D = neoclassics_variables.q_flux[1] * 1e-6 - q_neo_a = neoclassics_variables.q_flux[3] * 1e-6 - q_neo_T = neoclassics_variables.q_flux[2] * 1e-6 - - g_neo_e = ( - neoclassics_variables.gamma_flux[0] - * 1e-6 - * neoclassics_variables.temperatures[0] - ) - g_neo_D = ( - neoclassics_variables.gamma_flux[1] - * 1e-6 - * neoclassics_variables.temperatures[1] - ) - g_neo_a = ( - neoclassics_variables.gamma_flux[3] - * 1e-6 - * neoclassics_variables.temperatures[3] - ) - g_neo_T = ( - neoclassics_variables.gamma_flux[2] - * 1e-6 - * neoclassics_variables.temperatures[2] - ) - - dndt_neo_e = neoclassics_variables.gamma_flux[0] - dndt_neo_D = neoclassics_variables.gamma_flux[1] - dndt_neo_a = neoclassics_variables.gamma_flux[3] - dndt_neo_T = neoclassics_variables.gamma_flux[2] - - dndt_neo_fuel = ( - (dndt_neo_D + dndt_neo_T) - * physics_variables.a_plasma_surface - * impurity_radiation_module.radius_plasma_core_norm - ) - dmdt_neo_fuel = ( - dndt_neo_fuel * physics_variables.m_fuel_amu * constants.PROTON_MASS * 1.0e6 - ) # mg - dmdt_neo_fuel_from_e = ( - 4 - * dndt_neo_e - * physics_variables.a_plasma_surface - * impurity_radiation_module.radius_plasma_core_norm - * physics_variables.m_fuel_amu - * constants.PROTON_MASS - * 1.0e6 - ) # kg - - chi_neo_e = -( - neoclassics_variables.q_flux[0] - + neoclassics_variables.gamma_flux[0] * neoclassics_variables.temperatures[0] - ) / ( - neoclassics_variables.densities[0] * neoclassics_variables.dr_temperatures[0] - + neoclassics_variables.temperatures[0] - * neoclassics_variables.dr_densities[0] - ) - - chi_PROCESS_e = self.st_calc_eff_chi() - - nu_star_e = neoclassics_variables.nu_star_averaged[0] - nu_star_d = neoclassics_variables.nu_star_averaged[1] - nu_star_T = neoclassics_variables.nu_star_averaged[2] - nu_star_He = neoclassics_variables.nu_star_averaged[3] - - return ( - q_PROCESS, - q_PROCESS_r1, - q_neo, - gamma_neo, - total_q_neo, - total_q_neo_e, - q_neo_e, - q_neo_D, - q_neo_a, - q_neo_T, - g_neo_e, - g_neo_D, - g_neo_a, - g_neo_T, - dndt_neo_e, - dndt_neo_D, - dndt_neo_a, - dndt_neo_T, - dndt_neo_fuel, - dmdt_neo_fuel, - dmdt_neo_fuel_from_e, - chi_neo_e, - chi_PROCESS_e, - nu_star_e, - nu_star_d, - nu_star_T, - nu_star_He, - ) - - def st_calc_eff_chi(self): - volscaling = ( - physics_variables.vol_plasma - * stellarator_variables.f_r - * ( - impurity_radiation_module.radius_plasma_core_norm - * physics_variables.rminor - / stellarator_configuration.stella_config_rminor_ref - ) - ** 2 - ) - surfacescaling = ( - physics_variables.a_plasma_surface - * stellarator_variables.f_r - * ( - impurity_radiation_module.radius_plasma_core_norm - * physics_variables.rminor - / stellarator_configuration.stella_config_rminor_ref - ) - ) - - nominator = ( - physics_variables.f_p_alpha_plasma_deposited - * physics_variables.pden_alpha_total_mw - - physics_variables.pden_plasma_core_rad_mw - ) * volscaling - - # in fortran there was a 0*alphan term which I have removed for obvious reasons - # the following comment seems to describe this? - # "include alphan if chi should be incorporate density gradients too" - # but the history can be consulted if required (23/11/22 TN) - denominator = ( - ( - 3 - * physics_variables.nd_plasma_electron_on_axis - * constants.ELECTRON_CHARGE - * physics_variables.temp_plasma_electron_on_axis_kev - * 1e3 - * physics_variables.alphat - * impurity_radiation_module.radius_plasma_core_norm - * (1 - impurity_radiation_module.radius_plasma_core_norm**2) - ** (physics_variables.alphan + physics_variables.alphat - 1) - ) - * surfacescaling - * 1e-6 - ) - - return nominator / denominator - - def stheat(self, output: bool): - """Routine to calculate the auxiliary heating power - in a stellarator - author: P J Knight, CCFE, Culham Science Centre - outfile : input integer : output file unit - iprint : input integer : switch for writing to output file (1=yes) - This routine calculates the auxiliary heating power for - a stellarator device. - AEA FUS 172: Physics Assessment for the European Reactor Study - """ - if stellarator_variables.isthtr == 1: - current_drive_variables.p_hcd_ecrh_injected_total_mw = ( - current_drive_variables.p_hcd_primary_extra_heat_mw - ) - current_drive_variables.p_hcd_injected_ions_mw = 0 - current_drive_variables.p_hcd_injected_electrons_mw = ( - current_drive_variables.p_hcd_ecrh_injected_total_mw - ) - current_drive_variables.eta_hcd_primary_injector_wall_plug = ( - current_drive_variables.eta_ecrh_injector_wall_plug - ) - current_drive_variables.p_hcd_electric_total_mw = ( - current_drive_variables.p_hcd_injected_ions_mw - + current_drive_variables.p_hcd_injected_electrons_mw - ) / current_drive_variables.eta_hcd_primary_injector_wall_plug - elif stellarator_variables.isthtr == 2: - current_drive_variables.p_hcd_lowhyb_injected_total_mw = ( - current_drive_variables.p_hcd_primary_extra_heat_mw - ) - current_drive_variables.p_hcd_injected_ions_mw = 0 - current_drive_variables.p_hcd_injected_electrons_mw = ( - current_drive_variables.p_hcd_lowhyb_injected_total_mw - ) - current_drive_variables.eta_hcd_primary_injector_wall_plug = ( - current_drive_variables.eta_lowhyb_injector_wall_plug - ) - heat_transport_variables.p_hcd_electric_total_mw = ( - current_drive_variables.p_hcd_injected_ions_mw - + current_drive_variables.p_hcd_injected_electrons_mw - ) / current_drive_variables.eta_hcd_primary_injector_wall_plug - elif stellarator_variables.isthtr == 3: - ( - _effnbss, - f_p_beam_injected_ions, - current_drive_variables.f_p_beam_shine_through, - ) = self.current_drive.culnbi() - current_drive_variables.p_hcd_beam_injected_total_mw = ( - current_drive_variables.p_hcd_primary_extra_heat_mw - * (1 - current_drive_variables.f_p_beam_orbit_loss) - ) - current_drive_variables.p_beam_orbit_loss_mw = ( - current_drive_variables.p_hcd_primary_extra_heat_mw - * current_drive_variables.f_p_beam_orbit_loss - ) - current_drive_variables.p_hcd_injected_ions_mw = ( - current_drive_variables.p_hcd_beam_injected_total_mw - * f_p_beam_injected_ions - ) - current_drive_variables.p_hcd_injected_electrons_mw = ( - current_drive_variables.p_hcd_beam_injected_total_mw - * (1 - f_p_beam_injected_ions) - ) - current_drive_variables.eta_hcd_primary_injector_wall_plug = ( - current_drive_variables.eta_beam_injector_wall_plug - ) - current_drive_variables.p_hcd_electric_total_mw = ( - current_drive_variables.p_hcd_injected_ions_mw - + current_drive_variables.p_hcd_injected_electrons_mw - ) / current_drive_variables.eta_hcd_primary_injector_wall_plug - else: - raise ProcessValueError( - "Illegal value for isthtr", isthtr=stellarator_variables.isthtr - ) - - # Total injected power - - current_drive_variables.p_hcd_injected_total_mw = ( - current_drive_variables.p_hcd_injected_electrons_mw - + current_drive_variables.p_hcd_injected_ions_mw - ) - - # Calculate neutral beam current - - if abs(current_drive_variables.p_hcd_beam_injected_total_mw) > 1e-8: - current_drive_variables.c_beam_total = ( - 1e-3 - * (current_drive_variables.p_hcd_beam_injected_total_mw * 1e6) - / current_drive_variables.e_beam_kev - ) - else: - current_drive_variables.c_beam_total = 0 - - # Ratio of fusion to input (injection+ohmic) power - - if ( - abs( - current_drive_variables.p_hcd_injected_total_mw - + current_drive_variables.p_beam_orbit_loss_mw - + physics_variables.p_plasma_ohmic_mw - ) - < 1e-6 - ): - current_drive_variables.big_q_plasma = 1e18 - else: - current_drive_variables.big_q_plasma = ( - physics_variables.p_fusion_total_mw - / ( - current_drive_variables.p_hcd_injected_total_mw - + current_drive_variables.p_beam_orbit_loss_mw - + physics_variables.p_plasma_ohmic_mw - ) - ) - - if output: - po.oheadr(self.outfile, "Auxiliary Heating System") - - if stellarator_variables.isthtr == 1: - po.ocmmnt(self.outfile, "Electron Cyclotron Resonance Heating") - elif stellarator_variables.isthtr == 2: - po.ocmmnt(self.outfile, "Lower Hybrid Heating") - elif stellarator_variables.isthtr == 3: - po.ocmmnt(self.outfile, "Neutral Beam Injection Heating") - - if physics_variables.i_plasma_ignited == 1: - po.ocmmnt( - self.outfile, - "Ignited plasma; injected power only used for start-up phase", - ) - - po.oblnkl(self.outfile) - - po.ovarre( - self.outfile, - "Auxiliary power supplied to plasma (MW)", - "(p_hcd_primary_extra_heat_mw)", - current_drive_variables.p_hcd_primary_extra_heat_mw, - ) - po.ovarre( - self.outfile, - "Fusion gain factor Q", - "(big_q_plasma)", - current_drive_variables.big_q_plasma, - ) - - if abs(current_drive_variables.p_hcd_beam_injected_total_mw) > 1e-8: - po.ovarre( - self.outfile, - "Neutral beam energy (KEV)", - "(enbeam)", - current_drive_variables.enbeam, - ) - po.ovarre( - self.outfile, - "Neutral beam current (A)", - "(c_beam_total)", - current_drive_variables.c_beam_total, - ) - po.ovarre( - self.outfile, - "Fraction of beam energy to ions", - "(f_p_beam_injected_ions)", - f_p_beam_injected_ions, - ) - po.ovarre( - self.outfile, - "Neutral beam shine-through fraction", - "(f_p_beam_shine_through)", - current_drive_variables.f_p_beam_shine_through, - ) - po.ovarre( - self.outfile, - "Neutral beam orbit loss power (MW)", - "(p_beam_orbit_loss_mw)", - current_drive_variables.p_beam_orbit_loss_mw, - ) - po.ovarre( - self.outfile, - "Beam duct shielding thickness (m)", - "(dx_beam_shield)", - current_drive_variables.dx_beam_shield, - ) - po.ovarre( - self.outfile, - "R injection tangent / R-major", - "(f_radius_beam_tangency_rmajor)", - current_drive_variables.f_radius_beam_tangency_rmajor, - ) - po.ovarre( - self.outfile, - "Beam centreline tangency radius (m)", - "(radius_beam_tangency)", - current_drive_variables.radius_beam_tangency, - ) - po.ovarre( - self.outfile, - "Maximum possible tangency radius (m)", - "(radius_beam_tangency_max)", - current_drive_variables.radius_beam_tangency_max, - ) - po.ovarre( - self.outfile, - "Beam decay lengths to centre", - "(n_beam_decay_lengths_core)", - current_drive_variables.n_beam_decay_lengths_core, - ) - - -class Neoclassics: - @property - def no_roots(self): - return neoclassics_variables.roots.shape[0] - - def init_neoclassics(self, r_effin, eps_effin, iotain): - """Constructor of the neoclassics object from the effective radius, - epsilon effective and iota only. - """ - ( - neoclassics_variables.densities, - neoclassics_variables.temperatures, - neoclassics_variables.dr_densities, - neoclassics_variables.dr_temperatures, - ) = self.init_profile_values_from_PROCESS(r_effin) - neoclassics_variables.roots = np.array([ - 4.740718054080526184e-2, - 2.499239167531593919e-1, - 6.148334543927683749e-1, - 1.143195825666101451, - 1.836454554622572344, - 2.696521874557216147, - 3.725814507779509288, - 4.927293765849881879, - 6.304515590965073635, - 7.861693293370260349, - 9.603775985479263255, - 1.153654659795613924e1, - 1.366674469306423489e1, - 1.600222118898106771e1, - 1.855213484014315029e1, - 2.132720432178312819e1, - 2.434003576453269346e1, - 2.760555479678096091e1, - 3.114158670111123683e1, - 3.496965200824907072e1, - 3.911608494906788991e1, - 4.361365290848483056e1, - 4.850398616380419980e1, - 5.384138540650750571e1, - 5.969912185923549686e1, - 6.618061779443848991e1, - 7.344123859555988076e1, - 8.173681050672767867e1, - 9.155646652253683726e1, - 1.041575244310588886e2, - ]) - neoclassics_variables.weights = np.array([ - 1.160440860204388913e-1, - 2.208511247506771413e-1, - 2.413998275878537214e-1, - 1.946367684464170855e-1, - 1.237284159668764899e-1, - 6.367878036898660943e-2, - 2.686047527337972682e-2, - 9.338070881603925677e-3, - 2.680696891336819664e-3, - 6.351291219408556439e-4, - 1.239074599068830081e-4, - 1.982878843895233056e-5, - 2.589350929131392509e-6, - 2.740942840536013206e-7, - 2.332831165025738197e-8, - 1.580745574778327984e-9, - 8.427479123056716393e-11, - 3.485161234907855443e-12, - 1.099018059753451500e-13, - 2.588312664959080167e-15, - 4.437838059840028968e-17, - 5.365918308212045344e-19, - 4.393946892291604451e-21, - 2.311409794388543236e-23, - 7.274588498292248063e-26, - 1.239149701448267877e-28, - 9.832375083105887477e-32, - 2.842323553402700938e-35, - 1.878608031749515392e-39, - 8.745980440465011553e-45, - ]) - - neoclassics_variables.kt = self.neoclassics_calc_KT() - neoclassics_variables.nu = self.neoclassics_calc_nu() - neoclassics_variables.nu_star = self.neoclassics_calc_nu_star() - neoclassics_variables.nu_star_averaged = self.neoclassics_calc_nu_star_fromT( - iotain - ) - neoclassics_variables.vd = self.neoclassics_calc_vd() - - neoclassics_variables.d11_plateau = self.neoclassics_calc_D11_plateau() - - neoclassics_variables.d11_mono = self.neoclassics_calc_d11_mono( - eps_effin - ) # for using epseff - - neoclassics_variables.d111 = self.calc_integrated_radial_transport_coeffs( - index=1 - ) - neoclassics_variables.d112 = self.calc_integrated_radial_transport_coeffs( - index=2 - ) - neoclassics_variables.d113 = self.calc_integrated_radial_transport_coeffs( - index=3 - ) - - neoclassics_variables.gamma_flux = self.neoclassics_calc_gamma_flux( - neoclassics_variables.densities, - neoclassics_variables.temperatures, - neoclassics_variables.dr_densities, - neoclassics_variables.dr_temperatures, - ) - neoclassics_variables.q_flux = self.neoclassics_calc_q_flux() - - def init_profile_values_from_PROCESS(self, rho): - """Initializes the profile_values object from PROCESS' parabolic profiles""" - tempe = ( - physics_variables.temp_plasma_electron_on_axis_kev - * (1 - rho**2) ** physics_variables.alphat - * KEV - ) - tempT = ( - physics_variables.temp_plasma_ion_on_axis_kev - * (1 - rho**2) ** physics_variables.alphat - * KEV - ) - tempD = ( - physics_variables.temp_plasma_ion_on_axis_kev - * (1 - rho**2) ** physics_variables.alphat - * KEV - ) - tempa = ( - physics_variables.temp_plasma_ion_on_axis_kev - * (1 - rho**2) ** physics_variables.alphat - * KEV - ) - - dense = ( - physics_variables.nd_plasma_electron_on_axis - * (1 - rho**2) ** physics_variables.alphan - ) - densT = ( - (1 - physics_variables.f_plasma_fuel_deuterium) - * physics_variables.nd_plasma_ions_on_axis - * (1 - rho**2) ** physics_variables.alphan - ) - densD = ( - physics_variables.f_plasma_fuel_deuterium - * physics_variables.nd_plasma_ions_on_axis - * (1 - rho**2) ** physics_variables.alphan - ) - densa = ( - physics_variables.nd_plasma_alphas_vol_avg - * (1 + physics_variables.alphan) - * (1 - rho**2) ** physics_variables.alphan - ) - - # Derivatives in real space - dr_tempe = ( - -2.0 - * 1.0 - / physics_variables.rminor - * physics_variables.temp_plasma_electron_on_axis_kev - * rho - * (1.0 - rho**2) ** (physics_variables.alphat - 1.0) - * physics_variables.alphat - * KEV - ) - dr_tempT = ( - -2.0 - * 1.0 - / physics_variables.rminor - * physics_variables.temp_plasma_ion_on_axis_kev - * rho - * (1.0 - rho**2) ** (physics_variables.alphat - 1.0) - * physics_variables.alphat - * KEV - ) - dr_tempD = ( - -2.0 - * 1.0 - / physics_variables.rminor - * physics_variables.temp_plasma_ion_on_axis_kev - * rho - * (1.0 - rho**2) ** (physics_variables.alphat - 1.0) - * physics_variables.alphat - * KEV - ) - dr_tempa = ( - -2.0 - * 1.0 - / physics_variables.rminor - * physics_variables.temp_plasma_ion_on_axis_kev - * rho - * (1.0 - rho**2) ** (physics_variables.alphat - 1.0) - * physics_variables.alphat - * KEV - ) - - dr_dense = ( - -2.0 - * 1.0 - / physics_variables.rminor - * rho - * physics_variables.nd_plasma_electron_on_axis - * (1.0 - rho**2) ** (physics_variables.alphan - 1.0) - * physics_variables.alphan - ) - dr_densT = ( - -2.0 - * 1.0 - / physics_variables.rminor - * rho - * (1 - physics_variables.f_plasma_fuel_deuterium) - * physics_variables.nd_plasma_ions_on_axis - * (1.0 - rho**2) ** (physics_variables.alphan - 1.0) - * physics_variables.alphan - ) - dr_densD = ( - -2.0 - * 1.0 - / physics_variables.rminor - * rho - * physics_variables.f_plasma_fuel_deuterium - * physics_variables.nd_plasma_ions_on_axis - * (1.0 - rho**2) ** (physics_variables.alphan - 1.0) - * physics_variables.alphan - ) - dr_densa = ( - -2.0 - * 1.0 - / physics_variables.rminor - * rho - * physics_variables.nd_plasma_alphas_vol_avg - * (1 + physics_variables.alphan) - * (1.0 - rho**2) ** (physics_variables.alphan - 1.0) - * physics_variables.alphan - ) - - dens = np.array([dense, densD, densT, densa]) - temp = np.array([tempe, tempD, tempT, tempa]) - dr_dens = np.array([dr_dense, dr_densD, dr_densT, dr_densa]) - dr_temp = np.array([dr_tempe, dr_tempD, dr_tempT, dr_tempa]) - - return dens, temp, dr_dens, dr_temp - - def neoclassics_calc_KT(self): - """Calculates the energy on the given grid - which is given by the gauss laguerre roots. - """ - k = np.repeat((neoclassics_variables.roots / KEV)[:, np.newaxis], 4, axis=1) - - return (k * neoclassics_variables.temperatures).T - - def neoclassics_calc_nu(self): - """Calculates the collision frequency""" - mass = np.array([ - constants.ELECTRON_MASS, - constants.PROTON_MASS * 2.0, - constants.PROTON_MASS * 3.0, - constants.PROTON_MASS * 4.0, - ]) - z = np.array([-1.0, 1.0, 1.0, 2.0]) * constants.ELECTRON_CHARGE - - # transform the temperature back in eV - # Formula from L. Spitzer.Physics of fully ionized gases. Interscience, New York, 1962 - lnlambda = ( - 32.2 - - 1.15 * np.log10(neoclassics_variables.densities[0]) - + 2.3 - * np.log10(neoclassics_variables.temperatures[0] / constants.ELECTRON_CHARGE) - ) - - neoclassics_calc_nu = np.zeros((4, self.no_roots), order="F") - - for j in range(4): - for i in range(self.no_roots): - x = neoclassics_variables.roots[i] - for k in range(4): - xk = ( - (mass[k] / mass[j]) - * ( - neoclassics_variables.temperatures[j] - / neoclassics_variables.temperatures[k] - ) - * x - ) - expxk = np.exp(-xk) - t = 1.0 / (1.0 + 0.3275911 * np.sqrt(xk)) - erfn = ( - 1.0 - - t - * ( - 0.254829592 - + t - * ( - -0.284496736 - + t - * (1.421413741 + t * (-1.453152027 + t * 1.061405429)) - ) - ) - * expxk - ) - phixmgx = (1.0 - 0.5 / xk) * erfn + expxk / np.sqrt(np.pi * xk) - v = np.sqrt( - 2.0 * x * neoclassics_variables.temperatures[j] / mass[j] - ) - neoclassics_calc_nu[j, i] = neoclassics_calc_nu[ - j, i - ] + neoclassics_variables.densities[k] * ( - z[j] * z[k] - ) ** 2 * lnlambda * phixmgx / ( - 4.0 * np.pi * constants.EPSILON0**2 * mass[j] ** 2 * v**3 - ) - - return neoclassics_calc_nu - - def neoclassics_calc_nu_star(self): - """Calculates the normalized collision frequency""" - k = np.repeat(neoclassics_variables.roots[:, np.newaxis], 4, axis=1) - kk = (k * neoclassics_variables.temperatures).T - - mass = np.array([ - constants.ELECTRON_MASS, - constants.PROTON_MASS * 2.0, - constants.PROTON_MASS * 3.0, - constants.PROTON_MASS * 4.0, - ]) - - v = np.empty((4, self.no_roots)) - v[0, :] = constants.SPEED_LIGHT * np.sqrt( - 1.0 - (kk[0, :] / (mass[0] * constants.SPEED_LIGHT**2) + 1) ** (-1) - ) - v[1, :] = constants.SPEED_LIGHT * np.sqrt( - 1.0 - (kk[1, :] / (mass[1] * constants.SPEED_LIGHT**2) + 1) ** (-1) - ) - v[2, :] = constants.SPEED_LIGHT * np.sqrt( - 1.0 - (kk[2, :] / (mass[2] * constants.SPEED_LIGHT**2) + 1) ** (-1) - ) - v[3, :] = constants.SPEED_LIGHT * np.sqrt( - 1.0 - (kk[3, :] / (mass[3] * constants.SPEED_LIGHT**2) + 1) ** (-1) - ) - - return ( - physics_variables.rmajor - * neoclassics_variables.nu - / (neoclassics_variables.iota * v) - ) - - def neoclassics_calc_nu_star_fromT(self, iota): - """Calculates the collision frequency""" - temp = ( - np.array([ - physics_variables.temp_plasma_electron_vol_avg_kev, - physics_variables.temp_plasma_ion_vol_avg_kev, - physics_variables.temp_plasma_ion_vol_avg_kev, - physics_variables.temp_plasma_ion_vol_avg_kev, - ]) - * KEV - ) - density = np.array([ - physics_variables.nd_plasma_electrons_vol_avg, - physics_variables.nd_plasma_fuel_ions_vol_avg - * physics_variables.f_plasma_fuel_deuterium, - physics_variables.nd_plasma_fuel_ions_vol_avg - * (1 - physics_variables.f_plasma_fuel_deuterium), - physics_variables.nd_plasma_alphas_vol_avg, - ]) - - mass = np.array([ - constants.ELECTRON_MASS, - constants.PROTON_MASS * 2.0, - constants.PROTON_MASS * 3.0, - constants.PROTON_MASS * 4.0, - ]) - z = np.array([-1.0, 1.0, 1.0, 2.0]) * constants.ELECTRON_CHARGE - - # transform the temperature back in eV - # Formula from L. Spitzer.Physics of fully ionized gases. Interscience, New York, 1962 - lnlambda = ( - 32.2 - - 1.15 * np.log10(density[0]) - + 2.3 * np.log10(temp[0] / constants.ELECTRON_CHARGE) - ) - - neoclassics_calc_nu_star_fromT = np.zeros((4,)) - - for j in range(4): - v = np.sqrt(2.0 * temp[j] / mass[j]) - for k in range(4): - xk = (mass[k] / mass[j]) * (temp[j] / temp[k]) - - expxk = 0.0 - if xk < 200.0: - expxk = np.exp(-xk) - - t = 1.0 / (1.0 + 0.3275911 * np.sqrt(xk)) - erfn = ( - 1.0 - - t - * ( - 0.254829592 - + t - * ( - -0.284496736 - + t * (1.421413741 + t * (-1.453152027 + t * 1.061405429)) - ) - ) - * expxk - ) - phixmgx = (1.0 - 0.5 / xk) * erfn + expxk / np.sqrt(np.pi * xk) - neoclassics_calc_nu_star_fromT[j] = ( - neoclassics_calc_nu_star_fromT[j] - + density[k] - * (z[j] * z[k]) ** 2 - * lnlambda - * phixmgx - / (4.0 * np.pi * constants.EPSILON0**2 * mass[j] ** 2 * v**4) - * physics_variables.rmajor - / iota - ) - return neoclassics_calc_nu_star_fromT - - def neoclassics_calc_vd(self): - vde = ( - neoclassics_variables.roots - * neoclassics_variables.temperatures[0] - / ( - constants.ELECTRON_CHARGE - * physics_variables.rmajor - * physics_variables.b_plasma_toroidal_on_axis - ) - ) - vdD = ( - neoclassics_variables.roots - * neoclassics_variables.temperatures[1] - / ( - constants.ELECTRON_CHARGE - * physics_variables.rmajor - * physics_variables.b_plasma_toroidal_on_axis - ) - ) - vdT = ( - neoclassics_variables.roots - * neoclassics_variables.temperatures[2] - / ( - constants.ELECTRON_CHARGE - * physics_variables.rmajor - * physics_variables.b_plasma_toroidal_on_axis - ) - ) - vda = ( - neoclassics_variables.roots - * neoclassics_variables.temperatures[3] - / ( - 2.0 - * constants.ELECTRON_CHARGE - * physics_variables.rmajor - * physics_variables.b_plasma_toroidal_on_axis - ) - ) - - vd = np.empty((4, self.no_roots)) - - vd[0, :] = vde - vd[1, :] = vdD - vd[2, :] = vdT - vd[3, :] = vda - - return vd - - def neoclassics_calc_D11_plateau(self): - """Calculates the plateau transport coefficients (D11_star sometimes)""" - mass = np.array([ - constants.ELECTRON_MASS, - constants.PROTON_MASS * 2.0, - constants.PROTON_MASS * 3.0, - constants.PROTON_MASS * 4.0, - ]) - - v = np.empty((4, self.no_roots)) - v[0, :] = constants.SPEED_LIGHT * np.sqrt( - 1.0 - - (neoclassics_variables.kt[0, :] / (mass[0] * constants.SPEED_LIGHT**2) + 1) - ** (-1) - ) - v[1, :] = constants.SPEED_LIGHT * np.sqrt( - 1.0 - - (neoclassics_variables.kt[1, :] / (mass[1] * constants.SPEED_LIGHT**2) + 1) - ** (-1) - ) - v[2, :] = constants.SPEED_LIGHT * np.sqrt( - 1.0 - - (neoclassics_variables.kt[2, :] / (mass[2] * constants.SPEED_LIGHT**2) + 1) - ** (-1) - ) - v[3, :] = constants.SPEED_LIGHT * np.sqrt( - 1.0 - - (neoclassics_variables.kt[3, :] / (mass[3] * constants.SPEED_LIGHT**2) + 1) - ** (-1) - ) - - return ( - np.pi - / 4.0 - * neoclassics_variables.vd**2 - * physics_variables.rmajor - / neoclassics_variables.iota - / v - ) - - def neoclassics_calc_d11_mono(self, eps_eff): - """Calculates the monoenergetic radial transport coefficients - using epsilon effective - """ - return ( - 4.0 - / (9.0 * np.pi) - * (2.0 * eps_eff) ** (3.0 / 2.0) - * neoclassics_variables.vd**2 - / neoclassics_variables.nu - ) - - def calc_integrated_radial_transport_coeffs(self, index: int): - """Calculates the integrated radial transport coefficients (index `index`) - It uses Gauss laguerre integration - https://en.wikipedia.org/wiki/Gauss%E2%80%93Laguerre_quadrature - """ - return np.sum( - 2.0 - / np.sqrt(np.pi) - * neoclassics_variables.d11_mono - * neoclassics_variables.roots ** (index - 0.5) - * neoclassics_variables.weights, - axis=1, - ) - - def neoclassics_calc_gamma_flux( - self, densities, temperatures, dr_densities, dr_temperatures - ): - """Calculates the Energy flux by neoclassical particle transport""" - - z = np.array([-1.0, 1.0, 1.0, 2.0]) - - return ( - -densities - * neoclassics_variables.d111 - * ( - (dr_densities / densities - z * neoclassics_variables.er / temperatures) - + (neoclassics_variables.d112 / neoclassics_variables.d111 - 3.0 / 2.0) - * dr_temperatures - / temperatures - ) - ) - - def neoclassics_calc_q_flux(self): - """Calculates the Energy flux by neoclassicsal energy transport""" - - z = np.array([-1.0, 1.0, 1.0, 2.0]) - - return ( - -neoclassics_variables.densities - * neoclassics_variables.temperatures - * neoclassics_variables.d112 - * ( - ( - neoclassics_variables.dr_densities / neoclassics_variables.densities - - z * neoclassics_variables.er / neoclassics_variables.temperatures - ) - + (neoclassics_variables.d113 / neoclassics_variables.d112 - 3.0 / 2.0) - * neoclassics_variables.dr_temperatures - / neoclassics_variables.temperatures - ) - ) - - -def stinit(): - """Routine to initialise the variables relevant to stellarators - author: P J Knight, CCFE, Culham Science Centre - author: F Warmer, IPP Greifswald - - This routine initialises the variables relevant to stellarators. - Many of these may override the values set in routine - """ - if stellarator_variables.istell == 0: - return - - numerics.boundu[0] = 40.0 # allow higher aspect ratio - - # These lines switch off tokamak specifics (solenoid, pf coils, pulses etc.). - # Are they still up to date? (26/07/22 JL) - - # Build quantities - - build_variables.dr_cs = 0.0 - build_variables.iohcl = 0 - pfcoil_variables.f_z_cs_tf_internal = 0.0 - build_variables.dr_cs_tf_gap = 0.0 - build_variables.f_dr_tf_outboard_inboard = 1.0 - - # Physics quantities - - physics_variables.beta_norm_max = 0.0 - physics_variables.kappa95 = 1.0 - physics_variables.triang = 0.0 - physics_variables.q95 = 1.03 - - # Turn off current drive - - current_drive_variables.i_hcd_calculations = 0 - - # Times for different phases - - times_variables.t_plant_pulse_coil_precharge = 0.0 - times_variables.t_plant_pulse_plasma_current_ramp_up = 0.0 - times_variables.t_plant_pulse_burn = 3.15576e7 # one year - times_variables.t_plant_pulse_plasma_current_ramp_down = 0.0 - times_variables.t_plant_pulse_plasma_present = ( - times_variables.t_plant_pulse_plasma_current_ramp_up - + times_variables.t_plant_pulse_fusion_ramp - + times_variables.t_plant_pulse_burn - + times_variables.t_plant_pulse_plasma_current_ramp_down - ) - times_variables.t_plant_pulse_no_burn = ( - times_variables.t_plant_pulse_coil_precharge - + times_variables.t_plant_pulse_plasma_current_ramp_up - + times_variables.t_plant_pulse_plasma_current_ramp_down - + times_variables.t_plant_pulse_dwell - + times_variables.t_plant_pulse_fusion_ramp - ) - times_variables.t_plant_pulse_total = ( - times_variables.t_plant_pulse_coil_precharge - + times_variables.t_plant_pulse_plasma_current_ramp_up - + times_variables.t_plant_pulse_fusion_ramp - + times_variables.t_plant_pulse_burn - + times_variables.t_plant_pulse_plasma_current_ramp_down - + times_variables.t_plant_pulse_dwell - ) diff --git a/process/stellarator/__init__.py b/process/stellarator/__init__.py new file mode 100644 index 0000000000..e69de29bb2 diff --git a/process/stellarator/build.py b/process/stellarator/build.py new file mode 100644 index 0000000000..b6c738892d --- /dev/null +++ b/process/stellarator/build.py @@ -0,0 +1,436 @@ +from process import process_output as po +from process.data_structure import ( + build_variables, + fwbs_variables, + heat_transport_variables, + physics_variables, + stellarator_configuration, +) +from process.data_structure import ( + stellarator_variables as st, +) + + +def st_build(stellarator, f_output: bool): + """ + Routine to determine the build of a stellarator machine + author: P J Knight, CCFE, Culham Science Centre + author: F Warmer, IPP Greifswald + outfile : input integer : output file unit + iprint : input integer : switch for writing to output file (1=yes) + This routine determines the build of the stellarator machine. + The values calculated are based on the mean minor radius, etc., + as the actual radial and vertical build thicknesses vary with + toroidal angle. + """ + if fwbs_variables.blktmodel > 0: + build_variables.dr_blkt_inboard = ( + build_variables.blbuith + build_variables.blbmith + build_variables.blbpith + ) + build_variables.dr_blkt_outboard = ( + build_variables.blbuoth + build_variables.blbmoth + build_variables.blbpoth + ) + build_variables.dz_shld_upper = 0.5e0 * ( + build_variables.dr_shld_inboard + build_variables.dr_shld_outboard + ) + + # Top/bottom blanket thickness + + build_variables.dz_blkt_upper = 0.5e0 * ( + build_variables.dr_blkt_inboard + build_variables.dr_blkt_outboard + ) + + # First Wall + build_variables.dr_fw_inboard = ( + 2.0e0 * fwbs_variables.radius_fw_channel + 2.0e0 * fwbs_variables.dr_fw_wall + ) + build_variables.dr_fw_outboard = build_variables.dr_fw_inboard + + build_variables.dr_bore = physics_variables.rmajor - ( + build_variables.dr_cs + + build_variables.dr_cs_tf_gap + + build_variables.dr_tf_inboard + + build_variables.dr_shld_vv_gap_inboard + + build_variables.dr_vv_inboard + + build_variables.dr_shld_inboard + + build_variables.dr_blkt_inboard + + build_variables.dr_fw_inboard + + build_variables.dr_fw_plasma_gap_inboard + + physics_variables.rminor + ) + + # Radial build to centre of plasma (should be equal to physics_variables.rmajor) + build_variables.rbld = ( + build_variables.dr_bore + + build_variables.dr_cs + + build_variables.dr_cs_tf_gap + + build_variables.dr_tf_inboard + + build_variables.dr_shld_vv_gap_inboard + + build_variables.dr_vv_inboard + + build_variables.dr_shld_inboard + + build_variables.dr_blkt_inboard + + build_variables.dr_fw_inboard + + build_variables.dr_fw_plasma_gap_inboard + + physics_variables.rminor + ) + + # Bc stellarators cannot scale physics_variables.rminor reasonably well an additional constraint equation is required, + # that ensures that there is enough space between coils and plasma. + build_variables.required_radial_space = ( + build_variables.dr_tf_inboard / 2.0e0 + + build_variables.dr_shld_vv_gap_inboard + + build_variables.dr_vv_inboard + + build_variables.dr_shld_inboard + + build_variables.dr_blkt_inboard + + build_variables.dr_fw_inboard + + build_variables.dr_fw_plasma_gap_inboard + ) + + # derivative_min_LCFS_coils_dist for how strong the stellarator shape changes wrt to aspect ratio + build_variables.available_radial_space = ( + st.r_coil_minor * st.f_coil_shape + - st.f_st_rmajor * stellarator_configuration.stella_config_rminor_ref + ) + stellarator_configuration.stella_config_derivative_min_lcfs_coils_dist * ( + physics_variables.rminor + - st.f_st_rmajor * stellarator_configuration.stella_config_rminor_ref + ) + + # Radius to inner edge of inboard shield + build_variables.r_shld_inboard_inner = ( + physics_variables.rmajor + - physics_variables.rminor + - build_variables.dr_fw_plasma_gap_inboard + - build_variables.dr_fw_inboard + - build_variables.dr_blkt_inboard + - build_variables.dr_shld_inboard + ) + + # Radius to outer edge of outboard shield + build_variables.r_shld_outboard_outer = ( + physics_variables.rmajor + + physics_variables.rminor + + build_variables.dr_fw_plasma_gap_outboard + + build_variables.dr_fw_outboard + + build_variables.dr_blkt_outboard + + build_variables.dr_shld_outboard + ) + + # Thickness of outboard TF coil legs + build_variables.dr_tf_outboard = build_variables.dr_tf_inboard + + # Radius to centre of outboard TF coil legs + + build_variables.dr_shld_vv_gap_outboard = build_variables.gapomin + build_variables.r_tf_outboard_mid = ( + build_variables.r_shld_outboard_outer + + build_variables.dr_vv_outboard + + build_variables.dr_shld_vv_gap_outboard + + 0.5e0 * build_variables.dr_tf_outboard + ) + + # Height to inside edge of TF coil + # Roughly equal to average of (inboard build from TF coil to plasma + # centre) and (outboard build from plasma centre to TF coil) + + build_variables.z_tf_inside_half = 0.5e0 * ( + ( + build_variables.dr_shld_vv_gap_inboard + + build_variables.dr_vv_inboard + + build_variables.dr_shld_inboard + + build_variables.dr_blkt_inboard + + build_variables.dr_fw_inboard + + build_variables.dr_fw_plasma_gap_inboard + + physics_variables.rminor + ) + + ( + physics_variables.rminor + + build_variables.dr_fw_plasma_gap_outboard + + build_variables.dr_fw_outboard + + build_variables.dr_blkt_outboard + + build_variables.dr_shld_outboard + + build_variables.dr_vv_outboard + + build_variables.dr_shld_vv_gap_outboard + ) + ) + + # Outer divertor strike point radius, set equal to major radius + + build_variables.rspo = physics_variables.rmajor + + # First wall area: scales with minor radius + + # Average minor radius of the first wall + awall = physics_variables.rminor + 0.5e0 * ( + build_variables.dr_fw_plasma_gap_inboard + + build_variables.dr_fw_plasma_gap_outboard + ) + build_variables.a_fw_total = ( + physics_variables.a_plasma_surface * awall / physics_variables.rminor + ) + + if heat_transport_variables.ipowerflow == 0: + build_variables.a_fw_total = ( + 1.0e0 - fwbs_variables.fhole + ) * build_variables.a_fw_total + else: + build_variables.a_fw_total = ( + 1.0e0 + - fwbs_variables.fhole + - fwbs_variables.f_ster_div_single + - fwbs_variables.f_a_fw_outboard_hcd + ) * build_variables.a_fw_total + + if f_output: + # Print out device build + output(stellarator) + + +def output(stellarator): + po.oheadr(stellarator.outfile, "Radial Build") + + po.ovarre( + stellarator.outfile, + "Avail. Space (m)", + "(available_radial_space)", + build_variables.available_radial_space, + ) + po.ovarre( + stellarator.outfile, + "Req. Space (m)", + "(required_radial_space)", + build_variables.required_radial_space, + ) + + radius = 0.0e0 + po.obuild(stellarator.outfile, "Device centreline", 0.0e0, radius) + + drbild = ( + build_variables.dr_bore + build_variables.dr_cs + build_variables.dr_cs_tf_gap + ) + radius = radius + drbild + po.obuild(stellarator.outfile, "Machine dr_bore", drbild, radius, "(dr_bore)") + po.ovarre( + stellarator.outfile, "Machine build_variables.dr_bore (m)", "(dr_bore)", drbild + ) + + radius = radius + build_variables.dr_tf_inboard + po.obuild( + stellarator.outfile, + "Coil inboard leg", + build_variables.dr_tf_inboard, + radius, + "(dr_tf_inboard)", + ) + po.ovarre( + stellarator.outfile, + "Coil inboard leg (m)", + "(deltf)", + build_variables.dr_tf_inboard, + ) + + radius = radius + build_variables.dr_shld_vv_gap_inboard + po.obuild( + stellarator.outfile, + "Gap", + build_variables.dr_shld_vv_gap_inboard, + radius, + "(dr_shld_vv_gap_inboard)", + ) + po.ovarre( + stellarator.outfile, + "Gap (m)", + "(dr_shld_vv_gap_inboard)", + build_variables.dr_shld_vv_gap_inboard, + ) + + radius = radius + build_variables.dr_vv_inboard + po.obuild( + stellarator.outfile, + "Vacuum vessel", + build_variables.dr_vv_inboard, + radius, + "(dr_vv_inboard)", + ) + po.ovarre( + stellarator.outfile, + "Vacuum vessel radial thickness (m)", + "(dr_vv_inboard)", + build_variables.dr_vv_inboard, + ) + + radius = radius + build_variables.dr_shld_inboard + po.obuild( + stellarator.outfile, + "Inboard shield", + build_variables.dr_shld_inboard, + radius, + "(dr_shld_inboard)", + ) + po.ovarre( + stellarator.outfile, + "Inner radiation shield radial thickness (m)", + "(dr_shld_inboard)", + build_variables.dr_shld_inboard, + ) + + radius = radius + build_variables.dr_blkt_inboard + po.obuild( + stellarator.outfile, + "Inboard blanket", + build_variables.dr_blkt_inboard, + radius, + "(dr_blkt_inboard)", + ) + po.ovarre( + stellarator.outfile, + "Inboard blanket radial thickness (m)", + "(dr_blkt_inboard)", + build_variables.dr_blkt_inboard, + ) + + radius = radius + build_variables.dr_fw_inboard + po.obuild( + stellarator.outfile, + "Inboard first wall", + build_variables.dr_fw_inboard, + radius, + "(dr_fw_inboard)", + ) + po.ovarre( + stellarator.outfile, + "Inboard first wall radial thickness (m)", + "(dr_fw_inboard)", + build_variables.dr_fw_inboard, + ) + + radius = radius + build_variables.dr_fw_plasma_gap_inboard + po.obuild( + stellarator.outfile, + "Inboard scrape-off", + build_variables.dr_fw_plasma_gap_inboard, + radius, + "(dr_fw_plasma_gap_inboard)", + ) + po.ovarre( + stellarator.outfile, + "Inboard scrape-off radial thickness (m)", + "(dr_fw_plasma_gap_inboard)", + build_variables.dr_fw_plasma_gap_inboard, + ) + + radius = radius + physics_variables.rminor + po.obuild( + stellarator.outfile, + "Plasma geometric centre", + physics_variables.rminor, + radius, + "(rminor)", + ) + + radius = radius + physics_variables.rminor + po.obuild( + stellarator.outfile, + "Plasma outboard edge", + physics_variables.rminor, + radius, + "(rminor)", + ) + + radius = radius + build_variables.dr_fw_plasma_gap_outboard + po.obuild( + stellarator.outfile, + "Outboard scrape-off", + build_variables.dr_fw_plasma_gap_outboard, + radius, + "(dr_fw_plasma_gap_outboard)", + ) + po.ovarre( + stellarator.outfile, + "Outboard scrape-off radial thickness (m)", + "(dr_fw_plasma_gap_outboard)", + build_variables.dr_fw_plasma_gap_outboard, + ) + + radius = radius + build_variables.dr_fw_outboard + po.obuild( + stellarator.outfile, + "Outboard first wall", + build_variables.dr_fw_outboard, + radius, + "(dr_fw_outboard)", + ) + po.ovarre( + stellarator.outfile, + "Outboard first wall radial thickness (m)", + "(dr_fw_outboard)", + build_variables.dr_fw_outboard, + ) + + radius = radius + build_variables.dr_blkt_outboard + po.obuild( + stellarator.outfile, + "Outboard blanket", + build_variables.dr_blkt_outboard, + radius, + "(dr_blkt_outboard)", + ) + po.ovarre( + stellarator.outfile, + "Outboard blanket radial thickness (m)", + "(dr_blkt_outboard)", + build_variables.dr_blkt_outboard, + ) + + radius = radius + build_variables.dr_shld_outboard + po.obuild( + stellarator.outfile, + "Outboard shield", + build_variables.dr_shld_outboard, + radius, + "(dr_shld_outboard)", + ) + po.ovarre( + stellarator.outfile, + "Outer radiation shield radial thickness (m)", + "(dr_shld_outboard)", + build_variables.dr_shld_outboard, + ) + + radius = radius + build_variables.dr_vv_outboard + po.obuild( + stellarator.outfile, + "Vacuum vessel", + build_variables.dr_vv_outboard, + radius, + "(dr_vv_outboard)", + ) + + radius = radius + build_variables.dr_shld_vv_gap_outboard + po.obuild( + stellarator.outfile, + "Gap", + build_variables.dr_shld_vv_gap_outboard, + radius, + "(dr_shld_vv_gap_outboard)", + ) + po.ovarre( + stellarator.outfile, + "Gap (m)", + "(dr_shld_vv_gap_outboard)", + build_variables.dr_shld_vv_gap_outboard, + ) + + radius = radius + build_variables.dr_tf_outboard + po.obuild( + stellarator.outfile, + "Coil outboard leg", + build_variables.dr_tf_outboard, + radius, + "(dr_tf_outboard)", + ) + po.ovarre( + stellarator.outfile, + "Coil outboard leg radial thickness (m)", + "(dr_tf_outboard)", + build_variables.dr_tf_outboard, + ) diff --git a/process/stellarator/coils/__init__.py b/process/stellarator/coils/__init__.py new file mode 100644 index 0000000000..e69de29bb2 diff --git a/process/stellarator/coils/calculate.py b/process/stellarator/coils/calculate.py new file mode 100644 index 0000000000..c1ebfa8eac --- /dev/null +++ b/process/stellarator/coils/calculate.py @@ -0,0 +1,547 @@ +import logging + +import numpy as np + +import process.stellarator.coils.forces as forces +from process.data_structure import ( + build_variables, + constraint_variables, + rebco_variables, + stellarator_configuration, + stellarator_variables, + tfcoil_variables, +) +from process.stellarator.coils.coils import bmax_from_awp, intersect, jcrit_from_material +from process.stellarator.coils.mass import calculate_coils_mass +from process.stellarator.coils.output import write +from process.stellarator.coils.quench import calculate_quench_protection + +logger = logging.getLogger(__name__) + + +def st_coil(stellarator, output: bool): + """ + This routine calculates the properties of the coils for + a stellarator device. + author: J Lion, IPP Greifswald + outfile : input integer : output file unit + iprint : input integer : switch for writing to output file (1=yes) + + Some precalculated effective parameters for a stellarator power + plant design are used as the basis for the calculations. The coils + are assumed to be a fixed shape, but are scaled in size + appropriately for the machine being modelled. + """ + r_coil_major = stellarator_variables.r_coil_major + r_coil_minor = stellarator_variables.r_coil_minor + + ####################################################################################### + calculate_winding_pack_geometry() + + # Total coil current (MA) + coilcurrent = calculate_current() + + awp_rad, a_tf_wp_no_insulation, a_tf_wp_with_insulation, f_a_scu_of_wp = ( + winding_pack_total_size(r_coil_major, r_coil_minor, coilcurrent) + ) + + ####################################################################################### + # Casing calculations + calculate_casing() + + ####################################################################################### + # Port calculations + calculate_vertical_ports() + calculate_horizontal_ports() + + ####################################################################################### + # General Coil Geometry values + # + calculate_coil_toroidal_thickness() + calculate_coil_radial_thickness() + + calculate_coil_cross_sectional_area(a_tf_wp_with_insulation) + + calculate_coil_half_widths() + + calculate_plasma_facing_coil_area() + + coil_coil_gap, _ = calculate_coil_coil_toroidal_gap(r_coil_major, r_coil_minor) + + calculate_coils_summary_variables(coilcurrent, r_coil_major, r_coil_minor, awp_rad) + + inductance = calculate_inductnace(r_coil_minor) + calculate_stored_magnetic_energy(r_coil_minor) + + # Coil dimensions + build_variables.z_tf_inside_half = ( + 0.5e0 + * stellarator_configuration.stella_config_maximal_coil_height + * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) + ) # [m] maximum half-height of coil + + # [m] estimated average length of a coil + tfcoil_variables.len_tf_coil = ( + stellarator_configuration.stella_config_coillength + * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) + / tfcoil_variables.n_tf_coils + ) + + # [m^2] Total surface area of toroidal shells covering coils + tfcoil_variables.tfcryoarea = ( + stellarator_configuration.stella_config_coilsurface + * stellarator_variables.f_st_rmajor + * ( + stellarator_variables.r_coil_minor + / stellarator_configuration.stella_config_coil_rminor + ) + * 1.1e0 + ) + # 1.1 to scale it out a bit, as the shell must be bigger than WP + + # Minimal bending radius: + min_bending_radius = ( + stellarator_configuration.stella_config_min_bend_radius + * stellarator_variables.f_st_rmajor + / (1.0 - tfcoil_variables.dr_tf_wp_with_insulation / (2.0 * r_coil_minor)) + ) + + # End of general coil geometry values + + ####################################################################################### + # Coil_mases calculations + calculate_coils_mass(a_tf_wp_with_insulation, a_tf_wp_no_insulation) + + ####################################################################################### + # Quench protection: + f_vv_actual = calculate_quench_protection(coilcurrent) + + # + ####################################################################################### + # Forces scaling # + forces.calculate_max_force_density(a_tf_wp_no_insulation) + forces.calculate_maximum_stress() + + # Units: MN/m + max_force_density_mnm = forces.calculate_max_force_density_mnm() + # + max_lateral_force_density = forces.calculate_max_lateral_force_density( + a_tf_wp_no_insulation + ) + max_radial_force_density = forces.calculate_max_radial_force_density( + a_tf_wp_no_insulation + ) + # + # F = f*V = B*j*V \propto B/B0 * I/I0 * A0/A * A/A0 * len/len0 + centering_force_max_mn = forces.calculate_centering_force_max_mn() + centering_force_min_mn = forces.calculate_centering_force_min_mn() + centering_force_avg_mn = forces.calculate_centering_force_avg_mn() + # + #################################### + + if output: + write( + stellarator=stellarator, + a_tf_wp_no_insulation=a_tf_wp_no_insulation, + centering_force_avg_mn=centering_force_avg_mn, + centering_force_max_mn=centering_force_max_mn, + centering_force_min_mn=centering_force_min_mn, + coilcoilgap=coil_coil_gap, + coppera_m2=rebco_variables.coppera_m2, + coppera_m2_max=rebco_variables.coppera_m2_max, + f_a_scu_of_wp=f_a_scu_of_wp, + f_vv_actual=f_vv_actual, + fiooic=constraint_variables.fiooic, + inductance=inductance, + max_force_density=tfcoil_variables.max_force_density, + max_force_density_mnm=max_force_density_mnm, + max_lateral_force_density=max_lateral_force_density, + max_radial_force_density=max_radial_force_density, + min_bending_radius=min_bending_radius, + r_coil_major=r_coil_major, + r_coil_minor=r_coil_minor, + sig_tf_wp=tfcoil_variables.sig_tf_wp, + dx_tf_turn_general=tfcoil_variables.dx_tf_turn_general, + t_tf_superconductor_quench=tfcoil_variables.t_tf_superconductor_quench, + toroidalgap=tfcoil_variables.toroidalgap, + allowed_quench_voltage=tfcoil_variables.v_tf_coil_dump_quench_max_kv, + quench_voltage=tfcoil_variables.v_tf_coil_dump_quench_kv, + ) + + +def calculate_coil_toroidal_thickness(): + tfcoil_variables.dx_tf_inboard_out_toroidal = ( + tfcoil_variables.dx_tf_wp_primary_toroidal + + 2.0e0 * tfcoil_variables.dx_tf_side_case_min + + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation + ) # [m] Thickness of inboard leg in toroidal direction + + +def calculate_coil_radial_thickness(): + """Thickness of inboard and outboard leg in radial direction""" + # [m] Thickness of inboard leg in radial direction + build_variables.dr_tf_inboard = ( + tfcoil_variables.dr_tf_nose_case + + tfcoil_variables.dr_tf_wp_with_insulation + + tfcoil_variables.dr_tf_plasma_case + + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation + ) + # [m] Thickness of outboard leg in radial direction (same as inboard) + build_variables.dr_tf_outboard = build_variables.dr_tf_inboard + + +def calculate_coil_cross_sectional_area(a_tf_wp_with_insulation): + # [m^2] overall coil cross-sectional area + # (assuming inboard and outboard leg are the same) + tfcoil_variables.a_tf_leg_outboard = ( + build_variables.dr_tf_inboard * tfcoil_variables.dx_tf_inboard_out_toroidal + ) + # [m^2] Cross-sectional area of surrounding case + tfcoil_variables.a_tf_coil_inboard_case = ( + build_variables.dr_tf_inboard * tfcoil_variables.dx_tf_inboard_out_toroidal + ) - a_tf_wp_with_insulation + + +def calculate_coil_half_widths(): + # [m] Half-width of side of coil nearest torus centreline + tfcoil_variables.tfocrn = 0.5e0 * tfcoil_variables.dx_tf_inboard_out_toroidal + # [m] Half-width of side of coil nearest plasma + tfcoil_variables.tficrn = 0.5e0 * tfcoil_variables.dx_tf_inboard_out_toroidal + + +def calculate_plasma_facing_coil_area(): + # [m^2] Total surface area of coil side facing plasma: inboard region + tfcoil_variables.tfsai = ( + tfcoil_variables.n_tf_coils + * tfcoil_variables.dx_tf_inboard_out_toroidal + * 0.5e0 + * tfcoil_variables.len_tf_coil + ) + # [m^2] Total surface area of coil side facing plasma: outboard region (same as inboard) + tfcoil_variables.tfsao = tfcoil_variables.tfsai + + +def calculate_coil_coil_toroidal_gap(r_coil_major, r_coil_minor): + """ + [m] Minimal distance in toroidal direction between two stellarator coils + Consistency with coil width is checked in constraint equation 82 + """ + # [m] Toroidal gap between two coil filaments + tfcoil_variables.toroidalgap = ( + stellarator_configuration.stella_config_dmin + * (r_coil_major - r_coil_minor) + / ( + stellarator_configuration.stella_config_coil_rmajor + - stellarator_configuration.stella_config_coil_rminor + ) + ) + # Left-Over coil gap between two coils (m) + coilcoilgap = ( + tfcoil_variables.toroidalgap - tfcoil_variables.dx_tf_inboard_out_toroidal + ) + return coilcoilgap, tfcoil_variables.toroidalgap + + +def calculate_coils_summary_variables(coilcurrent, r_coil_major, r_coil_minor, awp_rad): + """Variables for ALL coils.""" + # [m^2] Total area of all coil legs (midplane) + tfcoil_variables.a_tf_inboard_total = ( + tfcoil_variables.n_tf_coils * tfcoil_variables.a_tf_leg_outboard + ) + # [A] Total current in ALL coils + tfcoil_variables.c_tf_total = tfcoil_variables.n_tf_coils * coilcurrent * 1.0e6 + # [A / m^2] overall current density + tfcoil_variables.oacdcp = ( + tfcoil_variables.c_tf_total / tfcoil_variables.a_tf_inboard_total + ) + # [m] radius of peak field occurrence, average + tfcoil_variables.r_b_tf_inboard_peak_symmetric = ( + r_coil_major - r_coil_minor + awp_rad + ) + # jlion: not sure what this will be used for. Not very + # useful for stellarators + + +def calculate_inductnace(r_coil_minor): + """This uses the reference value for the inductance and scales it with a^2/R (toroid inductance scaling)""" + return ( + stellarator_configuration.stella_config_inductance + / stellarator_variables.f_st_rmajor + * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) ** 2 + * stellarator_variables.f_st_n_coils**2 + ) + + +def calculate_stored_magnetic_energy(r_coil_minor): + """[GJ] Total magnetic energy""" + tfcoil_variables.e_tf_magnetic_stored_total_gj = ( + 0.5e0 + * ( + stellarator_configuration.stella_config_inductance + / stellarator_variables.f_st_rmajor + * (r_coil_minor / stellarator_configuration.stella_config_coil_rminor) ** 2 + * stellarator_variables.f_st_n_coils**2 + ) + * (tfcoil_variables.c_tf_total / tfcoil_variables.n_tf_coils) ** 2 + * 1.0e-9 + ) + + +def calculate_winding_pack_geometry(): + """ + Winding Pack Geometry: for one conductor + This one conductor will just be multiplied later to fit the winding pack size. + """ + # [m] Dimension of square cable space inside insulation + # and case of the conduit of each turn + dx_tf_turn_cable_space_average = tfcoil_variables.dx_tf_turn_general - 2.0e0 * ( + tfcoil_variables.dx_tf_turn_steel + tfcoil_variables.dx_tf_turn_insulation + ) # dx_tf_turn_cable_space_average = t_w + if dx_tf_turn_cable_space_average < 0: + logger.warning( + "Warning: Negative cable space dimension in TF coil winding pack. Check input parameters." + ) + logger.info( + "dx_tf_turn_cable_space_average is negative. Check t_turn, tfcoil_variables.dx_tf_turn_steel and dx_tf_turn_insulation." + ) + # [m^2] Cross-sectional area of cable space per turn + tfcoil_variables.a_tf_turn_cable_space_no_void = ( + 0.9e0 * dx_tf_turn_cable_space_average**2 + ) # 0.9 to include some rounded corners. (tfcoil_variables.a_tf_turn_cable_space_no_void = pi (dx_tf_turn_cable_space_average/2)**2 = pi/4 *dx_tf_turn_cable_space_average**2 for perfect round conductor). This factor depends on how round the corners are. + # [m^2] Cross-sectional area of conduit case per turn + tfcoil_variables.a_tf_turn_steel = ( + dx_tf_turn_cable_space_average + 2.0e0 * tfcoil_variables.dx_tf_turn_steel + ) ** 2 - tfcoil_variables.a_tf_turn_cable_space_no_void + + +def calculate_current(): + """ + Recalculate the coil current from global stellarator configuration and variables: + coilcurrent = f_b * stella_config_i0 * f_r / f_n + Update stellarator_variables.f_i + """ + coilcurrent = ( + stellarator_variables.f_st_b + * stellarator_configuration.stella_config_i0 + * stellarator_variables.f_st_rmajor + / stellarator_variables.f_st_n_coils + ) + stellarator_variables.f_st_i_total = ( + coilcurrent / stellarator_configuration.stella_config_i0 + ) + return coilcurrent + + +def winding_pack_total_size( + r_coil_major: float, r_coil_minor: float, coilcurrent: float +): + # Winding Pack total size: + + n_it = 200 # number of iterations + + rhs = np.zeros((n_it,)) + lhs = np.zeros((n_it,)) + jcrit_vector = np.zeros((n_it,)) + wp_width_r = np.zeros((n_it,)) + b_max_k = np.zeros((n_it,)) + + for k in range(n_it): + # Sample coil winding pack + wp_width_r[k] = (r_coil_minor / 40.0e0) + (k / (n_it - 1e0)) * ( + r_coil_minor / 1.0e0 - r_coil_minor / 40.0e0 + ) + if tfcoil_variables.i_tf_sc_mat == 6: + wp_width_r[k] = (r_coil_minor / 150.0e0) + (k / (n_it - 1e0)) * ( + r_coil_minor / 1.0e0 - r_coil_minor / 150.0e0 + ) + + # B-field calculation + b_max_k[k] = bmax_from_awp( + wp_width_r[k], + coilcurrent, + tfcoil_variables.n_tf_coils, + r_coil_major, + r_coil_minor, + ) + # Two margins can be applied for jcrit: direct or by temperature margin. + # Temperature margin is implemented in the jcrit_vector definition, + # direct margin is implemented after jcrit is defined (equation below) + # jcrit for this bmax: + jcrit_vector[k] = jcrit_from_material( + b_max_k[k], + tfcoil_variables.tftmp + tfcoil_variables.tmargmin, + tfcoil_variables.i_tf_sc_mat, + tfcoil_variables.b_crit_upper_nbti, + tfcoil_variables.bcritsc, + tfcoil_variables.f_a_tf_turn_cable_copper, + tfcoil_variables.fhts, + tfcoil_variables.t_crit_nbti, + tfcoil_variables.tcritsc, + tfcoil_variables.f_a_tf_turn_cable_space_extra_void, + tfcoil_variables.j_tf_wp, + ) # Get here a temperature margin from tfcoil_variables.tmargtf. + + # The operation current density weighted with the global iop/icrit fraction + lhs[:] = constraint_variables.fiooic * jcrit_vector + + # Superconductor fraction in wp + fraction_area_superconductor_of_wp = ( + ( + tfcoil_variables.a_tf_turn_cable_space_no_void + * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void) + ) + * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_copper) + / (tfcoil_variables.dx_tf_turn_general**2) + ) + # print *, "f_a_scu_of_wp. ",f_a_scu_of_wp,"Awp min: ",Awp(1) + + rhs[:] = coilcurrent / ( + wp_width_r**2 + / stellarator_configuration.stella_config_wp_ratio + * fraction_area_superconductor_of_wp + ) # f_a_scu_of_wp should be the fraction of the sc that is in the winding pack. + + wp_width_r_min = ( + r_coil_minor / 10.0e0 + ) ** 2 # Initial guess for intersection routine + if tfcoil_variables.i_tf_sc_mat == 6: + wp_width_r_min = ( + r_coil_minor / 20.0e0 + ) ** 2 # If REBCO, : start at smaller winding pack ratios + + # Find the intersection between LHS and RHS (or: how much awp do I need to get to the desired coil current) + wp_width_r_min = intersect(wp_width_r, lhs, wp_width_r, rhs, wp_width_r_min) + + # Maximum field at superconductor surface (T) + wp_width_r_min = max(tfcoil_variables.dx_tf_turn_general**2, wp_width_r_min) + + # Recalculate tfcoil_variables.b_tf_inboard_peak_symmetric at the found awp_min: + tfcoil_variables.b_tf_inboard_peak_symmetric = bmax_from_awp( + wp_width_r_min, + coilcurrent, + tfcoil_variables.n_tf_coils, + r_coil_major, + r_coil_minor, + ) + + # Winding pack toroidal, radial cross-sections (m) + awp_tor = ( + wp_width_r_min / stellarator_configuration.stella_config_wp_ratio + ) # Toroidal dimension + awp_rad = wp_width_r_min # Radial dimension + + tfcoil_variables.dx_tf_wp_primary_toroidal = ( + awp_tor # [m] toroidal thickness of winding pack + ) + tfcoil_variables.dx_tf_wp_secondary_toroidal = ( + awp_tor # [m] toroidal thickness of winding pack (region in front) + ) + tfcoil_variables.dr_tf_wp_with_insulation = ( + awp_rad # [m] radial thickness of winding pack + ) + + # [m^2] winding-pack cross sectional area including insulation (not global) + a_tf_wp_with_insulation = ( + tfcoil_variables.dr_tf_wp_with_insulation + + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation + ) * ( + tfcoil_variables.dx_tf_wp_primary_toroidal + + 2.0e0 * tfcoil_variables.dx_tf_wp_insulation + ) + + a_tf_wp_no_insulation = awp_tor * awp_rad # [m^2] winding-pack cross sectional area + tfcoil_variables.j_tf_wp = ( + coilcurrent * 1.0e6 / a_tf_wp_no_insulation + ) # [A/m^2] winding pack current density + tfcoil_variables.n_tf_coil_turns = a_tf_wp_no_insulation / ( + tfcoil_variables.dx_tf_turn_general**2 + ) # estimated number of turns for a given turn size (not global). Take at least 1. + tfcoil_variables.c_tf_turn = ( + coilcurrent * 1.0e6 / tfcoil_variables.n_tf_coil_turns + ) # [A] current per turn - estimation + # [m^2] Total conductor cross-sectional area, taking account of void area + tfcoil_variables.a_tf_wp_conductor = ( + tfcoil_variables.a_tf_turn_cable_space_no_void + * tfcoil_variables.n_tf_coil_turns + * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void) + ) + # [m^2] Void area in cable, for He + tfcoil_variables.a_tf_wp_extra_void = ( + tfcoil_variables.a_tf_turn_cable_space_no_void + * tfcoil_variables.n_tf_coil_turns + * tfcoil_variables.f_a_tf_turn_cable_space_extra_void + ) + # [m^2] Insulation area (not including ground-wall) + tfcoil_variables.a_tf_coil_wp_turn_insulation = tfcoil_variables.n_tf_coil_turns * ( + tfcoil_variables.dx_tf_turn_general**2 + - tfcoil_variables.a_tf_turn_steel + - tfcoil_variables.a_tf_turn_cable_space_no_void + ) + # [m^2] Structure area for cable + tfcoil_variables.a_tf_wp_steel = ( + tfcoil_variables.n_tf_coil_turns * tfcoil_variables.a_tf_turn_steel + ) + + return ( + awp_rad, + a_tf_wp_no_insulation, + a_tf_wp_with_insulation, + fraction_area_superconductor_of_wp, + ) + + +def calculate_casing(): + """ + Coil case thickness (m). Here assumed to be constant until something better comes up. + case_thickness_constant = tfcoil_variables.dr_tf_nose_case #0.2e0 # ? + Leave this constant for now... Check this## Should be scaled with forces I think. + For now assumed to be constant in a bolted plate model. + """ + # [m] coil case thickness outboard distance (radial) + tfcoil_variables.dr_tf_plasma_case = tfcoil_variables.dr_tf_nose_case + # dr_tf_nose_case = case_thickness_constant/2.0e0 # [m] coil case thickness inboard distance (radial). + + # [m] coil case thickness toroidal distance (toroidal) + tfcoil_variables.dx_tf_side_case_min = tfcoil_variables.dr_tf_nose_case + + +def calculate_vertical_ports(): + # Maximal toroidal port size (vertical ports) (m) + # The maximal distance is correct but the vertical extension of this port is not clear# + # This is simplified for now and can be made more accurate in the future# + stellarator_variables.vporttmax = ( + 0.4e0 + * stellarator_configuration.stella_config_max_portsize_width + * stellarator_variables.f_st_rmajor + / stellarator_variables.f_st_n_coils + ) # This is not accurate yet. Needs more insight# + + # Maximal poloidal port size (vertical ports) (m) + stellarator_variables.vportpmax = ( + 2.0 * stellarator_variables.vporttmax + ) # Simple approximation + + # Maximal vertical port clearance area (m2) + stellarator_variables.vportamax = ( + stellarator_variables.vporttmax * stellarator_variables.vportpmax + ) + + +def calculate_horizontal_ports(): + # Maximal toroidal port size (horizontal ports) (m) + stellarator_variables.hporttmax = ( + 0.8e0 + * stellarator_configuration.stella_config_max_portsize_width + * stellarator_variables.f_st_rmajor + / stellarator_variables.f_st_n_coils + ) # Factor 0.8 to take the variation with height into account + + # Maximal poloidal port size (horizontal ports) (m) + stellarator_variables.hportpmax = ( + 2.0e0 * stellarator_variables.hporttmax + ) # Simple approximation + + # Maximal horizontal port clearance area (m2) + stellarator_variables.hportamax = ( + stellarator_variables.hporttmax * stellarator_variables.hportpmax + ) diff --git a/process/stellarator/coils/coils.py b/process/stellarator/coils/coils.py new file mode 100644 index 0000000000..9599eb9b7e --- /dev/null +++ b/process/stellarator/coils/coils.py @@ -0,0 +1,265 @@ +import logging + +import numpy as np + +import process.superconductors as superconductors +from process.data_structure import ( + stellarator_configuration, +) +from process.exceptions import ProcessValueError + +logger = logging.getLogger(__name__) + + +def jcrit_from_material( + b_max, + t_helium, + i_tf_sc_mat, + b_crit_upper_nbti, + b_crit_sc, + f_a_tf_turn_cable_copper, + f_hts, + t_crit_nbti, + t_crit_sc, + f_a_tf_turn_cable_space_extra_void, + j_wp, +): + strain = -0.005 # for now a small value + f_he = f_a_tf_turn_cable_space_extra_void # this is helium fraction in the superconductor (set it to the fixed global variable here) + + f_tf_conductor_copper = ( + f_a_tf_turn_cable_copper # fcutfsu is a global variable. Is the copper fraction + ) + # of a cable conductor. + + if i_tf_sc_mat == 1: # ITER Nb3Sn critical surface parameterization + bc20m = 32.97 # these are values taken from sctfcoil.f90 + tc0m = 16.06 + + # j_crit_sc returned by itersc is the critical current density in the + # superconductor - not the whole strand, which contains copper + if b_max > bc20m: + j_crit_sc = 1.0e-9 # Set to a small nonzero value + else: + ( + j_crit_sc, + _bcrit, + _tcrit, + ) = superconductors.itersc(t_helium, b_max, strain, bc20m, tc0m) + + # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable + j_crit_cable = j_crit_sc * (1.0 - f_tf_conductor_copper) * (1.0e0 - f_he) + + # This is needed right now. Can we change it later? + j_crit_sc = max(1.0e-9, j_crit_sc) + j_crit_cable = max(1.0e-9, j_crit_cable) + + elif i_tf_sc_mat == 2: + # Bi-2212 high temperature superconductor parameterization + # Current density in a strand of Bi-2212 conductor + # N.B. jcrit returned by bi2212 is the critical current density + # in the strand, not just the superconducting portion. + # The parameterization for j_crit_cable assumes a particular strand + # composition that does not require a user-defined copper fraction, + # so this is irrelevant in this model + + jstrand = j_wp / (1 - f_he) + # jstrand = 0 # as far as I can tell this will always be 0 + # because jwp was never set in fortran (so 0) + + j_crit_cable, tmarg = superconductors.bi2212( + b_max, jstrand, t_helium, f_hts + ) # bi2212 outputs j_crit_cable + j_crit_sc = j_crit_cable / (1 - f_tf_conductor_copper) + _tcrit = t_helium + tmarg + elif i_tf_sc_mat == 3: # NbTi data + bc20m = 15.0 + tc0m = 9.3 + c0 = 1.0 + + if b_max > bc20m: + j_crit_sc = 1.0e-9 # Set to a small nonzero value + else: + j_crit_sc, _tcrit = superconductors.jcrit_nbti( + t_helium, + b_max, + c0, + bc20m, + tc0m, + ) + # I dont need tcrit here so dont use it. + + # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable + j_crit_cable = j_crit_sc * (1 - f_tf_conductor_copper) * (1 - f_he) + + # This is needed right now. Can we change it later? + j_crit_sc = max(1.0e-9, j_crit_sc) + j_crit_cable = max(1.0e-9, j_crit_cable) + elif i_tf_sc_mat == 4: # As (1), but user-defined parameters + bc20m = b_crit_sc + tc0m = t_crit_sc + j_crit_sc, _bcrit, _tcrit = superconductors.itersc( + t_helium, b_max, strain, bc20m, tc0m + ) + # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable + j_crit_cable = j_crit_sc * (1 - f_tf_conductor_copper) * (1 - f_he) + elif i_tf_sc_mat == 5: # WST Nb3Sn parameterisation + bc20m = 32.97 + tc0m = 16.06 + + # j_crit_sc returned by itersc is the critical current density in the + # superconductor - not the whole strand, which contains copper + + j_crit_sc, _bcrit, _tcrit = superconductors.western_superconducting_nb3sn( + t_helium, + b_max, + strain, + bc20m, + tc0m, + ) + # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable + j_crit_cable = j_crit_sc * (1 - f_tf_conductor_copper) * (1 - f_he) + elif i_tf_sc_mat == 6: # ! "REBCO" 2nd generation HTS superconductor in CrCo strand + j_crit_sc, _validity = superconductors.jcrit_rebco(t_helium, b_max, 0) + j_crit_sc = max(1.0e-9, j_crit_sc) + # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable + j_crit_cable = j_crit_sc * (1 - f_tf_conductor_copper) * (1 - f_he) + + elif i_tf_sc_mat == 7: # Durham Ginzburg-Landau Nb-Ti parameterisation + bc20m = b_crit_upper_nbti + tc0m = t_crit_nbti + j_crit_sc, _bcrit, _tcrit = superconductors.gl_nbti( + t_helium, b_max, strain, bc20m, tc0m + ) + # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable + j_crit_cable = j_crit_sc * (1 - f_tf_conductor_copper) * (1 - f_he) + elif i_tf_sc_mat == 8: + bc20m = 429 + tc0m = 185 + j_crit_sc, _bcrit, _tcrit = superconductors.gl_rebco( + t_helium, b_max, strain, bc20m, tc0m + ) + # A0 calculated for tape cross section already + # j_crit_cable = j_crit_sc * non-copper fraction of conductor * conductor fraction of cable + j_crit_cable = j_crit_sc * (1 - f_tf_conductor_copper) * (1 - f_he) + else: + raise ProcessValueError( + "Illegal value for i_pf_superconductor", i_tf_sc_mat=i_tf_sc_mat + ) + + return j_crit_sc * 1e-6 + + +def intersect(x1, y1, x2, y2, xin): + """Routine to find the x (abscissa) intersection point of two curves + each defined by tabulated (x,y) values + author: P J Knight, CCFE, Culham Science Centre + x1(1:n1) : input real array : x values for first curve + y1(1:n1) : input real array : y values for first curve + n1 : length of arrays x1, y1 + x2(1:n2) : input real array : x values for first curve + y2(1:n2) : input real array : y values for first curve + n2 : length of arrays x2, y2 + xin : initial guess for intersection point + x value at point of intersection on exit + This routine estimates the x point (abscissa) at which two curves + defined by tabulated (x,y) values intersect, using simple + linear interpolation and the Newton-Raphson method. + The routine will stop with an error message if no crossing point + is found within the x ranges of the two curves. + """ + x = xin + n1 = len(x1) + n2 = len(x2) + + xmin = max(np.amin(x1), np.amin(x2)) + xmax = min(np.max(x1), np.amax(x2)) + + if xmin >= xmax: + logger.error( + f"X ranges not overlapping. {np.amin(x1)=} {np.amin(x2)=} " + f"{np.amax(x1)=} {np.amax(x2)=}" + ) + + # Ensure input guess for x is within this range + if x < xmin: + x = xmin + elif x > xmax: + x = xmax + + # Find overall y range, and set tolerance + # in final difference in y values + + ymin = min(np.amin(y1), np.amin(y2)) + ymax = max(np.max(y1), np.max(y2)) + + epsy = 1.0e-6 * (ymax - ymin) + + # Finite difference dx + + dx = 0.01e0 / max(n1, n2) * (xmax - xmin) + + for _i in range(100): + # Find difference in y values at x + + y01 = np.interp(x, x1, y1) + y02 = np.interp(x, x2, y2) + y = y01 - y02 + + if abs(y) < epsy: + break + + # Find difference in y values at x+dx + + y01 = np.interp(x + dx, x1, y1) + y02 = np.interp(x + dx, x2, y2) + yright = y01 - y02 + + # Find difference in y values at x-dx + + y01 = np.interp(x - dx, x1, y1) + y02 = np.interp(x - dx, x2, y2) + yleft = y01 - y02 + + # Adjust x using Newton-Raphson method + + x = x - 2.0e0 * dx * y / (yright - yleft) + + if x < xmin: + logger.error( + f"X has dropped below Xmin; X={x} has been set equal to Xmin={xmin}" + ) + x = xmin + break + + if x > xmax: + logger.error( + f"X has risen above Xmax; X={x} has been set equal to Xmax={xmin}" + ) + x = xmax + break + else: + logger.error("Convergence too slow; X may be wrong...") + + return x + + +def bmax_from_awp(wp_width_radial, current, n_tf_coils, r_coil_major, r_coil_minor): + """Returns a fitted function for bmax for stellarators + + author: J Lion, IPP Greifswald + Returns a fitted function for bmax in dependece + of the winding pack. The stellarator type config + is taken from the parent scope. + """ + + return ( + 2e-1 # this is mu x 1e6, to use current in MA + * current + * n_tf_coils + / (r_coil_major - r_coil_minor) + * ( + stellarator_configuration.stella_config_a1 + + stellarator_configuration.stella_config_a2 * r_coil_major / wp_width_radial + ) + ) diff --git a/process/stellarator/coils/forces.py b/process/stellarator/coils/forces.py new file mode 100644 index 0000000000..e8065afb18 --- /dev/null +++ b/process/stellarator/coils/forces.py @@ -0,0 +1,109 @@ +"""Module for coil force calculations in stellarators.""" + +from process.data_structure import ( + stellarator_configuration, + stellarator_variables, + tfcoil_variables, +) + + +def calculate_max_force_density(a_tf_wp_no_insulation): + """Calculate the maximum force density in the TF coil winding pack from scaling. [MN/m3]""" + + tfcoil_variables.max_force_density = ( + stellarator_configuration.stella_config_max_force_density + * stellarator_variables.f_st_i_total + / stellarator_variables.f_st_n_coils + * tfcoil_variables.b_tf_inboard_peak_symmetric + / stellarator_configuration.stella_config_wp_bmax + * stellarator_configuration.stella_config_wp_area + / a_tf_wp_no_insulation + ) + + +def calculate_max_force_density_mnm(): + """Calculate the maximum force per meter in the TF coil winding pack from scaling. [MN/m]""" + return ( + stellarator_configuration.stella_config_max_force_density_mnm + * stellarator_variables.f_st_i_total + / stellarator_variables.f_st_n_coils + * tfcoil_variables.b_tf_inboard_peak_symmetric + / stellarator_configuration.stella_config_wp_bmax + ) + + +def calculate_maximum_stress(): + """Approximate, very simple maxiumum stress (needed for limitation of icc 32), in Pa""" + tfcoil_variables.sig_tf_wp = ( + tfcoil_variables.max_force_density + * tfcoil_variables.dr_tf_wp_with_insulation + * 1.0e6 + ) + + +def calculate_max_lateral_force_density(a_tf_wp_no_insulation): + """Calculate the maximum lateral force density in the TF coil winding pack from scaling. [MN/m3]""" + return ( + stellarator_configuration.stella_config_max_lateral_force_density + * stellarator_variables.f_st_i_total + / stellarator_variables.f_st_n_coils + * tfcoil_variables.b_tf_inboard_peak_symmetric + / stellarator_configuration.stella_config_wp_bmax + * stellarator_configuration.stella_config_wp_area + / a_tf_wp_no_insulation + ) + + +def calculate_max_radial_force_density(a_tf_wp_no_insulation): + """Calculate the maximum radial force density in the TF coil winding pack from scaling. [MN/m3]""" + return ( + stellarator_configuration.stella_config_max_radial_force_density + * stellarator_variables.f_st_i_total + / stellarator_variables.f_st_n_coils + * tfcoil_variables.b_tf_inboard_peak_symmetric + / stellarator_configuration.stella_config_wp_bmax + * stellarator_configuration.stella_config_wp_area + / a_tf_wp_no_insulation + ) + + +def calculate_centering_force_max_mn(): + """Calculate the maximum centering force in the TF coils from scaling. [MN]""" + return ( + stellarator_configuration.stella_config_centering_force_max_mn + * stellarator_variables.f_st_i_total + / stellarator_variables.f_st_n_coils + * tfcoil_variables.b_tf_inboard_peak_symmetric + / stellarator_configuration.stella_config_wp_bmax + * stellarator_configuration.stella_config_coillength + / tfcoil_variables.n_tf_coils + / tfcoil_variables.len_tf_coil + ) + + +def calculate_centering_force_min_mn(): + """Calculate the minimum centering force in the TF coils from scaling. [MN]""" + return ( + stellarator_configuration.stella_config_centering_force_min_mn + * stellarator_variables.f_st_i_total + / stellarator_variables.f_st_n_coils + * tfcoil_variables.b_tf_inboard_peak_symmetric + / stellarator_configuration.stella_config_wp_bmax + * stellarator_configuration.stella_config_coillength + / tfcoil_variables.n_tf_coils + / tfcoil_variables.len_tf_coil + ) + + +def calculate_centering_force_avg_mn(): + """Calculate the average centering force in the TF coils from scaling. [MN]""" + return ( + stellarator_configuration.stella_config_centering_force_avg_mn + * stellarator_variables.f_st_i_total + / stellarator_variables.f_st_n_coils + * tfcoil_variables.b_tf_inboard_peak_symmetric + / stellarator_configuration.stella_config_wp_bmax + * stellarator_configuration.stella_config_coillength + / tfcoil_variables.n_tf_coils + / tfcoil_variables.len_tf_coil + ) diff --git a/process/stellarator/coils/mass.py b/process/stellarator/coils/mass.py new file mode 100644 index 0000000000..9bae1abe5a --- /dev/null +++ b/process/stellarator/coils/mass.py @@ -0,0 +1,119 @@ +"""Module for coil mass calculations in stellarators.""" + +from process import constants +from process.data_structure import fwbs_variables, tfcoil_variables + + +def calculate_coils_mass(a_tf_wp_with_insulation: float, a_tf_wp_no_insulation: float): + """ + Calculates the mass of stellarator coils by aggregating the masses of various coil components. + This function computes the masses of conductor constituents (casing, ground insulation, superconductor, copper), + conduit masses (steel and insulation), and then calculates the total conductor and coil masses. + Args: + a_tf_wp_with_insulation (float): Area of the toroidal field coil winding pack with insulation. + a_tf_wp_no_insulation (float): Area of the toroidal field coil winding pack without insulation. + Returns: + None: The function performs calculations and updates external state. + """ + + # Masses of conductor constituents + casing() + ground_insulation(a_tf_wp_with_insulation, a_tf_wp_no_insulation) + superconductor() + copper() + + # conduit masses + conduit_steel() + conduit_insulation() + + # Total masses + total_conductor() + total_coil() + + +def casing(): + """ + [kg] Mass of case + (no need for correction factors as is the case for tokamaks) + This is only correct if the winding pack is 'thin' (len_tf_coil>>sqrt(tfcoil_variables.a_tf_coil_inboard_case)). + """ + tfcoil_variables.m_tf_coil_case = ( + tfcoil_variables.len_tf_coil + * tfcoil_variables.a_tf_coil_inboard_case + * tfcoil_variables.den_tf_coil_case + ) + + +def ground_insulation(a_tf_wp_with_insulation, a_tf_wp_no_insulation): + """Mass of ground-wall insulation [kg] + (assumed to be same density/material as conduit insulation)""" + tfcoil_variables.m_tf_coil_wp_insulation = ( + tfcoil_variables.len_tf_coil + * (a_tf_wp_with_insulation - a_tf_wp_no_insulation) + * tfcoil_variables.den_tf_wp_turn_insulation + ) + + +def superconductor(): + """[kg] mass of Superconductor + a_tf_wp_coolant_channels is 0 for a stellarator. but keep this term for now.""" + tfcoil_variables.m_tf_coil_superconductor = ( + tfcoil_variables.len_tf_coil + * tfcoil_variables.n_tf_coil_turns + * tfcoil_variables.a_tf_turn_cable_space_no_void + * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void) + * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_copper) + - tfcoil_variables.len_tf_coil * tfcoil_variables.a_tf_wp_coolant_channels + ) * tfcoil_variables.dcond[tfcoil_variables.i_tf_sc_mat - 1] + + +def copper(): + """[kg] mass of Copper in conductor""" + tfcoil_variables.m_tf_coil_copper = ( + tfcoil_variables.len_tf_coil + * tfcoil_variables.n_tf_coil_turns + * tfcoil_variables.a_tf_turn_cable_space_no_void + * (1.0e0 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void) + * tfcoil_variables.f_a_tf_turn_cable_copper + - tfcoil_variables.len_tf_coil * tfcoil_variables.a_tf_wp_coolant_channels + ) * constants.den_copper + + +def conduit_steel(): + """[kg] mass of Steel conduit (sheath)""" + tfcoil_variables.m_tf_wp_steel_conduit = ( + tfcoil_variables.len_tf_coil + * tfcoil_variables.n_tf_coil_turns + * tfcoil_variables.a_tf_turn_steel + * fwbs_variables.den_steel + ) + # if (i_tf_sc_mat==6) tfcoil_variables.m_tf_wp_steel_conduit = fcondsteel * a_tf_wp_no_insulation *tfcoil_variables.len_tf_coil* fwbs_variables.denstl + + +def conduit_insulation(): + """Conduit insulation mass [kg] + (tfcoil_variables.a_tf_coil_wp_turn_insulation already contains tfcoil_variables.n_tf_coil_turns)""" + tfcoil_variables.m_tf_coil_wp_turn_insulation = ( + tfcoil_variables.len_tf_coil + * tfcoil_variables.a_tf_coil_wp_turn_insulation + * tfcoil_variables.den_tf_wp_turn_insulation + ) + + +def total_conductor(): + """[kg] Total conductor mass""" + tfcoil_variables.m_tf_coil_conductor = ( + tfcoil_variables.m_tf_coil_superconductor + + tfcoil_variables.m_tf_coil_copper + + tfcoil_variables.m_tf_wp_steel_conduit + + tfcoil_variables.m_tf_coil_wp_turn_insulation + ) + + +def total_coil(): + """[kg] Total coil mass""" + tfcoil_variables.m_tf_coils_total = ( + tfcoil_variables.m_tf_coil_case + + tfcoil_variables.m_tf_coil_conductor + + tfcoil_variables.m_tf_coil_wp_insulation + ) * tfcoil_variables.n_tf_coils diff --git a/process/stellarator/coils/output.py b/process/stellarator/coils/output.py new file mode 100644 index 0000000000..c6514ca37d --- /dev/null +++ b/process/stellarator/coils/output.py @@ -0,0 +1,493 @@ +from process import process_output as po +from process.data_structure import ( + build_variables, + stellarator_variables, + tfcoil_variables, +) + + +def write( + stellarator, + a_tf_wp_no_insulation, + centering_force_avg_mn, + centering_force_max_mn, + centering_force_min_mn, + coilcoilgap, + coppera_m2, + coppera_m2_max, + f_a_scu_of_wp, + f_vv_actual, + fiooic, + inductance, + max_force_density, + max_force_density_mnm, + max_lateral_force_density, + max_radial_force_density, + min_bending_radius, + r_coil_major, + r_coil_minor, + sig_tf_wp, + dx_tf_turn_general, + t_tf_superconductor_quench, + toroidalgap, + allowed_quench_voltage, + quench_voltage, +): + """Writes stellarator modular coil output to file + author: P J Knight, CCFE, Culham Science Centre + outfile : input integer : output file unit + This routine writes the stellarator modular coil results + to the output file. + None + """ + po.oheadr(stellarator.outfile, "Modular Coils") + + po.osubhd(stellarator.outfile, "General Coil Parameters :") + + po.ovarre( + stellarator.outfile, + "Number of modular coils", + "(n_tf_coils)", + tfcoil_variables.n_tf_coils, + ) + po.ovarre(stellarator.outfile, "Av. coil major radius", "(coil_r)", r_coil_major) + po.ovarre(stellarator.outfile, "Av. coil minor radius", "(coil_a)", r_coil_minor) + po.ovarre( + stellarator.outfile, + "Av. coil aspect ratio", + "(coil_aspect)", + r_coil_major / r_coil_minor, + ) + + po.ovarre( + stellarator.outfile, + "Cross-sectional area per coil (m2)", + "(tfarea/n_tf_coils)", + tfcoil_variables.a_tf_inboard_total / tfcoil_variables.n_tf_coils, + ) + po.ovarre( + stellarator.outfile, + "Total inboard leg radial thickness (m)", + "(dr_tf_inboard)", + build_variables.dr_tf_inboard, + ) + po.ovarre( + stellarator.outfile, + "Total outboard leg radial thickness (m)", + "(dr_tf_outboard)", + build_variables.dr_tf_outboard, + ) + po.ovarre( + stellarator.outfile, + "Inboard leg outboard half-width (m)", + "(tficrn)", + tfcoil_variables.tficrn, + ) + po.ovarre( + stellarator.outfile, + "Inboard leg inboard half-width (m)", + "(tfocrn)", + tfcoil_variables.tfocrn, + ) + po.ovarre( + stellarator.outfile, + "Outboard leg toroidal thickness (m)", + "(dx_tf_inboard_out_toroidal)", + tfcoil_variables.dx_tf_inboard_out_toroidal, + ) + po.ovarre( + stellarator.outfile, "Minimum coil distance (m)", "(toroidalgap)", toroidalgap + ) + po.ovarre( + stellarator.outfile, + "Minimal left gap between coils (m)", + "(coilcoilgap)", + coilcoilgap, + ) + po.ovarre( + stellarator.outfile, + "Minimum coil bending radius (m)", + "(min_bend_radius)", + min_bending_radius, + ) + po.ovarre( + stellarator.outfile, + "Mean coil circumference (m)", + "(len_tf_coil)", + tfcoil_variables.len_tf_coil, + ) + po.ovarre( + stellarator.outfile, + "Total current (MA)", + "(c_tf_total)", + 1.0e-6 * tfcoil_variables.c_tf_total, + ) + po.ovarre( + stellarator.outfile, + "Current per coil(MA)", + "(c_tf_total/n_tf_coils)", + 1.0e-6 * tfcoil_variables.c_tf_total / tfcoil_variables.n_tf_coils, + ) + po.ovarre( + stellarator.outfile, + "Winding pack current density (A/m2)", + "(j_tf_wp)", + tfcoil_variables.j_tf_wp, + ) + po.ovarre( + stellarator.outfile, + "Max allowable current density as restricted by quench (A/m2)", + "(j_tf_wp_quench_heat_max)", + tfcoil_variables.j_tf_wp_quench_heat_max, + ) + po.ovarre( + stellarator.outfile, + "Overall current density (A/m2)", + "(oacdcp)", + tfcoil_variables.oacdcp, + ) + po.ovarre( + stellarator.outfile, + "Maximum field on superconductor (T)", + "(b_tf_inboard_peak_symmetric)", + tfcoil_variables.b_tf_inboard_peak_symmetric, + ) + po.ovarre( + stellarator.outfile, + "Total Stored energy (GJ)", + "(e_tf_magnetic_stored_total_gj)", + tfcoil_variables.e_tf_magnetic_stored_total_gj, + ) + po.ovarre( + stellarator.outfile, "Inductance of TF Coils (H)", "(inductance)", inductance + ) + po.ovarre( + stellarator.outfile, + "Total mass of coils (kg)", + "(m_tf_coils_total)", + tfcoil_variables.m_tf_coils_total, + ) + + po.osubhd(stellarator.outfile, "Coil Geometry :") + + po.ovarre( + stellarator.outfile, + "Outboard leg centre radius (m)", + "(r_tf_outboard_mid)", + build_variables.r_tf_outboard_mid, + ) + po.ovarre( + stellarator.outfile, + "Maximum inboard edge height (m)", + "(z_tf_inside_half)", + build_variables.z_tf_inside_half, + ) + + po.osubhd(stellarator.outfile, "Conductor Information :") + po.ovarre( + stellarator.outfile, + "Superconductor mass per coil (kg)", + "(m_tf_coil_superconductor)", + tfcoil_variables.m_tf_coil_superconductor, + ) + po.ovarre( + stellarator.outfile, + "Copper mass per coil (kg)", + "(m_tf_coil_copper)", + tfcoil_variables.m_tf_coil_copper, + ) + po.ovarre( + stellarator.outfile, + "Steel conduit mass per coil (kg)", + "(m_tf_wp_steel_conduit)", + tfcoil_variables.m_tf_wp_steel_conduit, + ) + po.ovarre( + stellarator.outfile, + "Total conductor cable mass per coil (kg)", + "(m_tf_coil_conductor)", + tfcoil_variables.m_tf_coil_conductor, + ) + po.ovarre( + stellarator.outfile, + "Cable conductor + void area (m2)", + "(a_tf_turn_cable_space_no_void)", + tfcoil_variables.a_tf_turn_cable_space_no_void, + ) + po.ovarre( + stellarator.outfile, + "Cable space coolant fraction", + "(f_a_tf_turn_cable_space_extra_void)", + tfcoil_variables.f_a_tf_turn_cable_space_extra_void, + ) + po.ovarre( + stellarator.outfile, + "Conduit case thickness (m)", + "(dx_tf_turn_steel)", + tfcoil_variables.dx_tf_turn_steel, + ) + po.ovarre( + stellarator.outfile, + "Cable insulation thickness (m)", + "(dx_tf_turn_insulation)", + tfcoil_variables.dx_tf_turn_insulation, + ) + + ap = a_tf_wp_no_insulation + po.osubhd(stellarator.outfile, "Winding Pack Information :") + po.ovarre(stellarator.outfile, "Winding pack area", "(ap)", ap) + po.ovarre( + stellarator.outfile, + "Conductor fraction of winding pack", + "(a_tf_wp_conductor/ap)", + tfcoil_variables.a_tf_wp_conductor / ap, + ) + po.ovarre( + stellarator.outfile, + "Copper fraction of conductor", + "(f_a_tf_turn_cable_copper)", + tfcoil_variables.f_a_tf_turn_cable_copper, + ) + po.ovarre( + stellarator.outfile, + "Structure fraction of winding pack", + "(a_tf_wp_steel/ap)", + tfcoil_variables.a_tf_wp_steel / ap, + ) + po.ovarre( + stellarator.outfile, + "Insulator fraction of winding pack", + "(a_tf_coil_wp_turn_insulation/ap)", + tfcoil_variables.a_tf_coil_wp_turn_insulation / ap, + ) + po.ovarre( + stellarator.outfile, + "Helium fraction of winding pack", + "(a_tf_wp_extra_void/ap)", + tfcoil_variables.a_tf_wp_extra_void / ap, + ) + po.ovarre( + stellarator.outfile, + "Winding radial thickness (m)", + "(dr_tf_wp_with_insulation)", + tfcoil_variables.dr_tf_wp_with_insulation, + ) + po.ovarre( + stellarator.outfile, + "Winding toroidal thickness (m)", + "(dx_tf_wp_primary_toroidal)", + tfcoil_variables.dx_tf_wp_primary_toroidal, + ) + po.ovarre( + stellarator.outfile, + "Ground wall insulation thickness (m)", + "(dx_tf_wp_insulation)", + tfcoil_variables.dx_tf_wp_insulation, + ) + po.ovarre( + stellarator.outfile, + "Number of turns per coil", + "(n_tf_coil_turns)", + tfcoil_variables.n_tf_coil_turns, + ) + po.ovarre( + stellarator.outfile, + "Width of each turn (incl. insulation) (m)", + "(dx_tf_turn_general)", + dx_tf_turn_general, + ) + po.ovarre( + stellarator.outfile, + "Current per turn (A)", + "(c_tf_turn)", + tfcoil_variables.c_tf_turn, + ) + po.ovarre(stellarator.outfile, "jop/jcrit", "(fiooic)", fiooic) + po.ovarre( + stellarator.outfile, + "Current density in conductor area (A/m2)", + "(c_tf_total/a_tf_wp_conductor)", + 1.0e-6 + * tfcoil_variables.c_tf_total + / tfcoil_variables.n_tf_coils + / tfcoil_variables.a_tf_wp_conductor, + ) + po.ovarre( + stellarator.outfile, + "Current density in SC area (A/m2)", + "(c_tf_total/a_tf_wp_conductor/f_a_scu_of_wp)", + 1.0e-6 + * tfcoil_variables.c_tf_total + / tfcoil_variables.n_tf_coils + / ap + / f_a_scu_of_wp, + ) + po.ovarre( + stellarator.outfile, + "Superconductor faction of WP (1)", + "(f_a_scu_of_wp)", + f_a_scu_of_wp, + ) + + po.osubhd(stellarator.outfile, "Forces and Stress :") + po.ovarre( + stellarator.outfile, + "Maximal toroidally and radially av. force density (MN/m3)", + "(max_force_density)", + max_force_density, + ) + po.ovarre( + stellarator.outfile, + "Maximal force density (MN/m)", + "(max_force_density_Mnm)", + max_force_density_mnm, + ) + po.ovarre( + stellarator.outfile, + "Maximal stress (approx.) (MPa)", + "(sig_tf_wp)", + sig_tf_wp * 1.0e-6, + ) + + po.ovarre( + stellarator.outfile, + "Maximal lateral force density (MN/m3)", + "(max_lateral_force_density)", + max_lateral_force_density, + ) + po.ovarre( + stellarator.outfile, + "Maximal radial force density (MN/m3)", + "(max_radial_force_density)", + max_radial_force_density, + ) + + po.ovarre( + stellarator.outfile, + "Max. centering force (coil) (MN)", + "(centering_force_max_MN)", + centering_force_max_mn, + ) + po.ovarre( + stellarator.outfile, + "Min. centering force (coil) (MN)", + "(centering_force_min_MN)", + centering_force_min_mn, + ) + po.ovarre( + stellarator.outfile, + "Avg. centering force per coil (MN)", + "(centering_force_avg_MN)", + centering_force_avg_mn, + ) + + po.osubhd(stellarator.outfile, "Quench Restrictions :") + po.ovarre( + stellarator.outfile, + "Actual quench time (or time constant) (s)", + "(t_tf_superconductor_quench)", + t_tf_superconductor_quench, + ) + po.ovarre( + stellarator.outfile, + "Actual quench vaccuum vessel force density (MN/m^3)", + "(f_vv_actual)", + f_vv_actual, + ) + po.ovarre( + stellarator.outfile, + "Maximum allowed voltage during quench due to insulation (kV)", + "(v_tf_coil_dump_quench_max_kv)", + allowed_quench_voltage, + ) + po.ovarre( + stellarator.outfile, + "Actual quench voltage (kV)", + "(v_tf_coil_dump_quench_kv)", + quench_voltage, + "OP ", + ) + po.ovarre( + stellarator.outfile, + "Current (A) per mm^2 copper (A/mm2)", + "(coppera_m2)", + coppera_m2 * 1.0e-6, + ) + po.ovarre( + stellarator.outfile, + "Max Copper current fraction:", + "(coppera_m2/coppera_m2_max)", + coppera_m2 / coppera_m2_max, + ) + + po.osubhd(stellarator.outfile, "External Case Information :") + + po.ovarre( + stellarator.outfile, + "Case thickness, plasma side (m)", + "(dr_tf_plasma_case)", + tfcoil_variables.dr_tf_plasma_case, + ) + po.ovarre( + stellarator.outfile, + "Case thickness, outer side (m)", + "(dr_tf_nose_case)", + tfcoil_variables.dr_tf_nose_case, + ) + po.ovarre( + stellarator.outfile, + "Case toroidal thickness (m)", + "(dx_tf_side_case_min)", + tfcoil_variables.dx_tf_side_case_min, + ) + po.ovarre( + stellarator.outfile, + "Case area per coil (m2)", + "(a_tf_coil_inboard_case)", + tfcoil_variables.a_tf_coil_inboard_case, + ) + po.ovarre( + stellarator.outfile, + "External case mass per coil (kg)", + "(m_tf_coil_case)", + tfcoil_variables.m_tf_coil_case, + ) + + po.osubhd(stellarator.outfile, "Available Space for Ports :") + + po.ovarre( + stellarator.outfile, + "Max toroidal size of vertical ports (m)", + "(vporttmax)", + stellarator_variables.vporttmax, + ) + po.ovarre( + stellarator.outfile, + "Max poloidal size of vertical ports (m)", + "(vportpmax)", + stellarator_variables.vportpmax, + ) + po.ovarre( + stellarator.outfile, + "Max area of vertical ports (m2)", + "(vportamax)", + stellarator_variables.vportamax, + ) + po.ovarre( + stellarator.outfile, + "Max toroidal size of horizontal ports (m)", + "(hporttmax)", + stellarator_variables.hporttmax, + ) + po.ovarre( + stellarator.outfile, + "Max poloidal size of horizontal ports (m)", + "(hportpmax)", + stellarator_variables.hportpmax, + ) + po.ovarre( + stellarator.outfile, + "Max area of horizontal ports (m2)", + "(hportamax)", + stellarator_variables.hportamax, + ) diff --git a/process/stellarator/coils/quench.py b/process/stellarator/coils/quench.py new file mode 100644 index 0000000000..c487b98b5c --- /dev/null +++ b/process/stellarator/coils/quench.py @@ -0,0 +1,203 @@ +"""Module to calculate quench protection limits for stellarator coils""" + +import numpy as np + +from process.data_structure import ( + build_variables, + physics_variables, + rebco_variables, + superconducting_tf_coil_variables, + tfcoil_variables, +) + + +def calculate_quench_protection(coilcurrent): + """ + Calculate quench protecion limits for stellarator coils + Includes calculation of the vacuum vessel force density, quench protection current density + and max dump voltage during quench + coilcurrent : Total coils current (MA) + """ + # + # This copied from the tokamak module: + # Radial position of vacuum vessel [m] + rad_vv_in = ( + physics_variables.rmajor + - physics_variables.rminor + - build_variables.dr_fw_plasma_gap_inboard + - build_variables.dr_fw_inboard + - build_variables.dr_blkt_inboard + - build_variables.dr_shld_blkt_gap + - build_variables.dr_shld_inboard + ) + rad_vv_out = ( + physics_variables.rmajor + + physics_variables.rminor + + build_variables.dr_fw_plasma_gap_outboard + + build_variables.dr_fw_outboard + + build_variables.dr_blkt_outboard + + build_variables.dr_shld_blkt_gap + + build_variables.dr_shld_outboard + ) + + # Stellarator version is working on the W7-X scaling, so we should actual use vv r_major + # plasma r_major is just an approximation, but exact calculations require 3D geometry + # Maybe it can be added to the stella_config file in the future + rad_vv = physics_variables.rmajor + + # MN/m^3 + f_vv_actual = calculate_vv_max_force_density_from_W7X_scaling(rad_vv) + + # This approach merge stress model from tokamaks with induced force calculated from W7-X scaling + a_vv = (rad_vv_out + rad_vv_in) / (rad_vv_out - rad_vv_in) + zeta = 1 + ((a_vv - 1) * np.log((a_vv + 1) / (a_vv - 1)) / (2 * a_vv)) + + superconducting_tf_coil_variables.vv_stress_quench = ( + zeta * f_vv_actual * 1e6 * rad_vv_in + ) + + # comparison + # the new quench protection routine, see #1047 + tfcoil_variables.j_tf_wp_quench_heat_max = ( + calculate_quench_protection_current_density( + tau_quench=tfcoil_variables.t_tf_superconductor_quench, + t_detect=tfcoil_variables.t_tf_quench_detection, + f_cu=tfcoil_variables.f_a_tf_turn_cable_copper, + f_cond=1 - tfcoil_variables.f_a_tf_turn_cable_space_extra_void, + temp=tfcoil_variables.tftmp, + a_cable=tfcoil_variables.a_tf_turn_cable_space_no_void, + a_turn=tfcoil_variables.dx_tf_turn_general**2, + ) + ) + + # Also give the copper current density (copper A/m2) for REBCO quench calculations: + rebco_variables.coppera_m2 = ( + coilcurrent + * 1.0e6 + / ( + tfcoil_variables.a_tf_wp_conductor + * tfcoil_variables.f_a_tf_turn_cable_copper + ) + ) + + # Max volatage during fast discharge of TF coil (V) + # (note that tf_coil_variable is in kV, while calculation is in V) + tfcoil_variables.v_tf_coil_dump_quench_kv = ( + max_dump_voltage( + tf_energy_stored=( + tfcoil_variables.e_tf_magnetic_stored_total_gj + / tfcoil_variables.n_tf_coils + * 1.0e9 + ), + t_dump=tfcoil_variables.t_tf_superconductor_quench, + current=tfcoil_variables.c_tf_turn, + ) + / 1.0e3 + ) # turn into kV + + return f_vv_actual + + +def calculate_vv_max_force_density_from_W7X_scaling(rad_vv: float) -> float: + """Actual VV force density from scaling [MN/m^3] + Based on reference values from W-7X. + """ + force_density_ref = 2.54 # MN/m^3 + b_ref = 3.0 # T + i_total_ref = 1.3e6 * 50 + rminor_ref = 0.92 # m + tau_ref = 3.0 # s + rmajor_ref = 5.2 # m + dr_vv_ref = 14e-3 # m, thickness of VV + + return ( + force_density_ref + * ( + b_ref + / physics_variables.b_plasma_toroidal_on_axis + * i_total_ref + / tfcoil_variables.c_tf_total + * rminor_ref**2 + / physics_variables.rminor**2 + ) + ** (-1) + * ( + tau_ref + / tfcoil_variables.t_tf_superconductor_quench + * rmajor_ref + / rad_vv + * dr_vv_ref + / ((build_variables.dr_vv_inboard + build_variables.dr_vv_outboard) / 2) + ) + ) + + +def max_dump_voltage(tf_energy_stored: float, t_dump: float, current: float) -> float: + """ + Max volatage during fast discharge of TF coil (V) + tf_energy_stored : Energy stored in one TF coil (J) + t_dump : Dump time (sec) + current : Operating current (A) + """ + return 2 * (tf_energy_stored / t_dump) / current + + +def calculate_quench_protection_current_density( + tau_quench, t_detect, f_cu, f_cond, temp, a_cable, a_turn +): + """ + Calculates the current density limited by the protection limit. + + Simplified 0-D adiabatic heat balance "hotspot criterion" model. + + This is slightly diffrent that tokamak version (also diffrent from the stellarator paper). + We skip the superconduc6tor contribution (this should be more conservative in theory). + tau_quench : Quench time (s) + t_detect : Detection time (s) + f_cu : Copper fraction + f_cond : Conductor fraction + temp : peak helium coolant temperature in TF coils and PF coils (K) + a_cable : Cable space area (per turn) [m2] (Includes the area of voids and central helium channel) + a_turn : TF coil turn cross section area [m2] + """ + temp_k = [4, 14, 24, 34, 44, 54, 64, 74, 84, 94, 104, 114, 124] + q_cu_array_sa2m4 = [ + 1.08514e17, + 1.12043e17, + 1.12406e17, + 1.05940e17, + 9.49741e16, + 8.43757e16, + 7.56346e16, + 6.85924e16, + 6.28575e16, + 5.81004e16, + 5.40838e16, + 5.06414e16, + 4.76531e16, + ] + q_he_array_sa2m4 = [ + 3.44562e16, + 9.92398e15, + 4.90462e15, + 2.41524e15, + 1.26368e15, + 7.51617e14, + 5.01632e14, + 3.63641e14, + 2.79164e14, + 2.23193e14, + 1.83832e14, + 1.54863e14, + 1.32773e14, + ] + + q_he = np.interp(temp, temp_k, q_he_array_sa2m4) + q_cu = np.interp(temp, temp_k, q_cu_array_sa2m4) + + # This leaves out the contribution from the superconductor fraction for now + return (a_cable / a_turn) * np.sqrt( + 1 + / (0.5 * tau_quench + t_detect) + * (f_cu**2 * f_cond**2 * q_cu + f_cu * f_cond * (1 - f_cond) * q_he) + ) diff --git a/process/stellarator/denisty_limits.py b/process/stellarator/denisty_limits.py new file mode 100644 index 0000000000..5b42cef653 --- /dev/null +++ b/process/stellarator/denisty_limits.py @@ -0,0 +1,248 @@ +import logging +from copy import copy + +import numpy as np + +from process import process_output as po +from process.data_structure import ( + physics_variables, + stellarator_variables, +) +from process.exceptions import ProcessValueError + +logger = logging.getLogger(__name__) + + +def st_denisty_limits(stellarator, f_output): + """Routine to reiterate the physics loop + author: J Lion, IPP Greifswald + None + This routine reiterates some physics modules. + """ + + # Set the required value for icc=5 + physics_variables.nd_plasma_electrons_max = st_sudo_density_limit( + physics_variables.b_plasma_toroidal_on_axis, + physics_variables.p_plasma_loss_mw, + physics_variables.rmajor, + physics_variables.rminor, + ) + + # Calculates the ECRH parameters + + ne0_max_ECRH, bt_ecrh = st_d_limit_ecrh( + stellarator_variables.max_gyrotron_frequency, + physics_variables.b_plasma_toroidal_on_axis, + ) + + ne0_max_ECRH = min(physics_variables.nd_plasma_electron_on_axis, ne0_max_ECRH) + bt_ecrh = min(physics_variables.b_plasma_toroidal_on_axis, bt_ecrh) + + if f_output: + output( + stellarator, + bt_ecrh, + ne0_max_ECRH, + ) + + +def st_sudo_density_limit(b_plasma_toroidal_on_axis, powht, rmajor, rminor): + """Routine to calculate the Sudo density limit in a stellarator + author: P J Knight, CCFE, Culham Science Centre + bt : input real : Toroidal field on axis (T) + bt = b_plasma_toroidal_on_axis + powht : input real : Absorbed heating power (MW) + rmajor : input real : Plasma major radius (m) + rminor : input real : Plasma minor radius (m) + dlimit : output real : Maximum volume-averaged plasma density (/m3) + This routine calculates the density limit for a stellarator. + S.Sudo, Y.Takeiri, H.Zushi et al., Scalings of Energy Confinement + and Density Limit in Stellarator/Heliotron Devices, Nuclear Fusion + vol.30, 11 (1990). + """ + arg = powht * b_plasma_toroidal_on_axis / (rmajor * rminor * rminor) + + if arg <= 0.0e0: + raise ProcessValueError( + "Negative square root imminent", + arg=arg, + powht=powht, + bt=b_plasma_toroidal_on_axis, + rmajor=rmajor, + rminor=rminor, + ) + + # Maximum line-averaged electron density + + dnlamx = 0.25e20 * np.sqrt(arg) + + # Scale the result so that it applies to the volume-averaged + # electron density + + nd_plasma_electron_max_array = ( + dnlamx + * physics_variables.nd_plasma_electrons_vol_avg + / physics_variables.nd_plasma_electron_line + ) + + physics_variables.nd_plasma_electrons_max = nd_plasma_electron_max_array + + return nd_plasma_electron_max_array + + +def st_d_limit_ecrh(gyro_frequency_max, bt_input): + """Routine to calculate the density limit due to an ECRH heating scheme on axis + depending on an assumed maximal available gyrotron frequency. + author: J Lion, IPP Greifswald + gyro_frequency_max : input real : Maximal available Gyrotron frequency (1/s) NOT (rad/s) + bt : input real : Maximal magnetic field on axis (T) + dlimit_ecrh : output real : Maximum peak plasma density by ECRH constraints (/m3) + bt_max : output real : Maximum allowable b field for ecrh heating (T) + This routine calculates the density limit due to an ECRH heating scheme on axis + """ + gyro_frequency = min(1.76e11 * bt_input, gyro_frequency_max * 2.0e0 * np.pi) + + # Restrict b field to the maximal available gyrotron frequency + bt_max = (gyro_frequency_max * 2.0e0 * np.pi) / 1.76e11 + + # me*e0/e^2 * w^2 + ne0_max = max(0.0e0, 3.142077e-4 * gyro_frequency**2) + + # Check if parabolic profiles are used: + if physics_variables.i_plasma_pedestal == 0: + # Parabolic profiles used, use analytical formula: + dlimit_ecrh = ne0_max + else: + logger.error( + "It was used physics_variables.i_plasma_pedestal = 1 in a stellarator routine." + ) + + return dlimit_ecrh, bt_max + + +def power_at_ignition_point(stellarator, gyro_frequency_max, te0_available): + """Routine to calculate if the plasma is ignitable with the current values for the B field. Assumes + current ECRH achievable peak temperature (which is inaccurate as the cordey pass should be calculated) + author: J Lion, IPP Greifswald + gyro_frequency_max : input real : Maximal available Gyrotron frequency (1/s) NOT (rad/s) + te0_available : input real : Reachable peak electron temperature, reached by ECRH (KEV) + powerht_out : output real: Heating Power at ignition point (MW) + pscalingmw_out : output real: Heating Power loss at ignition point (MW) + This routine calculates the density limit due to an ECRH heating scheme on axis + Assumes current peak temperature (which is inaccurate as the cordey pass should be calculated) + Maybe use this: https://doi.org/10.1088/0029-5515/49/8/085026 + """ + te_old = copy(physics_variables.temp_plasma_electron_vol_avg_kev) + # Volume averaged physics_variables.te from te0_achievable + physics_variables.temp_plasma_electron_vol_avg_kev = te0_available / ( + 1.0e0 + physics_variables.alphat + ) + ne0_max, bt_ecrh_max = st_d_limit_ecrh( + gyro_frequency_max, physics_variables.b_plasma_toroidal_on_axis + ) + # Now go to point where ECRH is still available + # In density.. + dene_old = copy(physics_variables.nd_plasma_electrons_vol_avg) + physics_variables.nd_plasma_electrons_vol_avg = min( + dene_old, ne0_max / (1.0e0 + physics_variables.alphan) + ) + + # And B-field.. + bt_old = copy(physics_variables.b_plasma_toroidal_on_axis) + physics_variables.b_plasma_toroidal_on_axis = min( + bt_ecrh_max, physics_variables.b_plasma_toroidal_on_axis + ) + + stellarator.st_phys(False) + stellarator.st_phys( + False + ) # The second call seems to be necessary for all values to "converge" (and is sufficient) + + powerht_out = max( + copy(physics_variables.p_plasma_loss_mw), 0.00001e0 + ) # the radiation module sometimes returns negative heating power + pscalingmw_out = copy(physics_variables.pscalingmw) + + # Reverse it and do it again because anything more efficiently isn't suitable with the current implementation + # This is bad practice but seems to be necessary as of now: + physics_variables.temp_plasma_electron_vol_avg_kev = te_old + physics_variables.nd_plasma_electrons_vol_avg = dene_old + physics_variables.b_plasma_toroidal_on_axis = bt_old + + # The second call seems to be necessary for all values to "converge" (and is sufficient) + stellarator.st_phys(False) + stellarator.st_phys(False) + + return powerht_out, pscalingmw_out + + +def output(stellarator, bt_ecrh, ne0_max_ECRH): + po.oheadr(stellarator.outfile, "ECRH Ignition at lower values. Information:") + + po.ovarre( + stellarator.outfile, + "Maximal available gyrotron freq (input)", + "(max_gyro_frequency)", + stellarator_variables.max_gyrotron_frequency, + ) + + po.ovarre( + stellarator.outfile, + "Operating point: bfield", + "(b_plasma_toroidal_on_axis)", + physics_variables.b_plasma_toroidal_on_axis, + ) + + po.ovarre( + stellarator.outfile, + "Operating point: Peak density", + "(nd_plasma_electron_on_axis)", + physics_variables.nd_plasma_electron_on_axis, + ) + po.ovarre( + stellarator.outfile, + "Operating point: Peak temperature", + "(temp_plasma_electron_on_axis_kev)", + physics_variables.temp_plasma_electron_on_axis_kev, + ) + + po.ovarre(stellarator.outfile, "Ignition point: bfield (T)", "(bt_ecrh)", bt_ecrh) + po.ovarre( + stellarator.outfile, + "Ignition point: density (/m3)", + "(ne0_max_ECRH)", + ne0_max_ECRH, + ) + po.ovarre( + stellarator.outfile, + "Maximum reachable ECRH temperature (pseudo) (KEV)", + "(te0_ecrh_achievable)", + stellarator_variables.te0_ecrh_achievable, + ) + + powerht_local, pscalingmw_local = power_at_ignition_point( + stellarator, + stellarator_variables.max_gyrotron_frequency, + stellarator_variables.te0_ecrh_achievable, + ) + po.ovarre( + stellarator.outfile, + "Ignition point: Heating Power (MW)", + "(powerht_ecrh)", + powerht_local, + ) + po.ovarre( + stellarator.outfile, + "Ignition point: Loss Power (MW)", + "(pscalingmw_ecrh)", + pscalingmw_local, + ) + + if powerht_local >= pscalingmw_local: + po.ovarin( + stellarator.outfile, "Operation point ECRH ignitable?", "(ecrh_bool)", 1 + ) + else: + po.ovarin( + stellarator.outfile, "Operation point ECRH ignitable?", "(ecrh_bool)", 0 + ) diff --git a/process/stellarator/divertor.py b/process/stellarator/divertor.py new file mode 100644 index 0000000000..c07160ac97 --- /dev/null +++ b/process/stellarator/divertor.py @@ -0,0 +1,220 @@ +import numpy as np + +from process import constants +from process import process_output as po +from process.data_structure import ( + build_variables, + divertor_variables, + fwbs_variables, + physics_variables, + stellarator_variables, +) + + +def st_div(stellarator, f_output: bool): + """Routine to call the stellarator divertor model + author: P J Knight, CCFE, Culham Science Centre + author: F Warmer, IPP Greifswald + outfile : input integer : output file unit + iprint : input integer : switch for writing to output file (1=yes) + This routine calls the divertor model for a stellarator, + developed by Felix Warmer. + Stellarator Divertor Model for the Systems + Code PROCESS, F. Warmer, 21/06/2013 + """ + Theta = stellarator_variables.flpitch # ~bmn [rad] field line pitch + r = physics_variables.rmajor + p_div = physics_variables.p_plasma_separatrix_mw + alpha = divertor_variables.anginc + xi_p = divertor_variables.xpertin + T_scrape = divertor_variables.tdiv + + # Scrape-off temperature in Joules + + e = T_scrape * constants.ELECTRON_CHARGE + + # Sound speed of particles (m/s) + + c_s = np.sqrt(e / (physics_variables.m_fuel_amu * constants.UMASS)) + + # Island size (m) + + w_r = 4.0e0 * np.sqrt( + stellarator_variables.bmn + * r + / (stellarator_variables.shear * stellarator_variables.n_res) + ) + + # Perpendicular (to plate) distance from X-point to divertor plate (m) + + Delta = stellarator_variables.f_w * w_r + + # Length 'along' plasma (m) + + l_p = 2 * np.pi * r * (stellarator_variables.m_res) / stellarator_variables.n_res + + # Connection length from X-point to divertor plate (m) + + l_x_t = Delta / Theta + + # Power decay length (m) + + l_q = np.sqrt(xi_p * (l_x_t / c_s)) + + # Channel broadening length (m) + + l_b = np.sqrt(xi_p * l_p / (c_s)) + + # Channel broadening factor + + f_x = 1.0e0 + (l_b / (l_p * Theta)) + + # Length of a single divertor plate (m) + + l_d = f_x * l_p * (Theta / alpha) + + # Total length of divertor plates (m) + + l_t = 2.0e0 * stellarator_variables.n_res * l_d + + # Wetted area (m2) + + a_eff = l_t * l_q + + # Divertor plate width (m): assume total area is wetted area/stellarator_variables.fdivwet + + darea = a_eff / stellarator_variables.fdivwet + l_w = darea / l_t + + # Divertor heat load (MW/m2) + + q_div = stellarator_variables.f_asym * (p_div / a_eff) + + # Transfer to global variables + + divertor_variables.pflux_div_heat_load_mw = q_div + divertor_variables.a_div_surface_total = darea + + fwbs_variables.f_ster_div_single = darea / build_variables.a_fw_total + + if f_output: + output(stellarator, a_eff, l_d, l_w, f_x, l_q, w_r, Delta) + + +def output(stellarator, a_eff, l_d, l_w, f_x, l_q, w_r, Delta): + """ + Outputs a summary of divertor-related parameters and results to the stellartor object. + + Parameters: + stellarator: An object containing stellarator configuration and output handle. + a_eff (float): Effective divertor wetted area (m²). + l_d (float): Divertor plate length (m). + l_w (float): Divertor plate width (m). + f_x (float): Flux channel broadening factor. + l_q (float): Power decay width (m). + w_r (float): Island width (m). + Delta (float): Perpendicular distance from X-point to plate (m). + + The function writes various physical and geometric parameters related to the divertor, + including power, angles, heat transport coefficients, resonance numbers, field perturbations, + and other relevant quantities, to the output file associated with the stellarator object. + """ + + po.oheadr(stellarator.outfile, "Divertor") + + po.ovarre( + stellarator.outfile, + "Power to divertor (MW)", + "(p_plasma_separatrix_mw.)", + physics_variables.p_plasma_separatrix_mw, + ) + po.ovarre( + stellarator.outfile, + "Angle of incidence (deg)", + "(anginc)", + divertor_variables.anginc * 180.0e0 / np.pi, + ) + po.ovarre( + stellarator.outfile, + "Perp. heat transport coefficient (m2/s)", + "(xpertin)", + divertor_variables.xpertin, + ) + po.ovarre( + stellarator.outfile, + "Divertor plasma temperature (eV)", + "(tdiv)", + divertor_variables.tdiv, + ) + po.ovarre( + stellarator.outfile, + "Radiated power fraction in SOL", + "(f_rad)", + stellarator_variables.f_rad, + ) + po.ovarre( + stellarator.outfile, + "Heat load peaking factor", + "(f_asym)", + stellarator_variables.f_asym, + ) + po.ovarin( + stellarator.outfile, + "Poloidal resonance number", + "(m_res)", + stellarator_variables.m_res, + ) + po.ovarin( + stellarator.outfile, + "Toroidal resonance number", + "(n_res)", + stellarator_variables.n_res, + ) + po.ovarre( + stellarator.outfile, + "Relative radial field perturbation", + "(bmn)", + stellarator_variables.bmn, + ) + po.ovarre( + stellarator.outfile, + "Field line pitch (rad)", + "(flpitch)", + stellarator_variables.flpitch, + ) + po.ovarre( + stellarator.outfile, + "Island size fraction factor", + "(f_w)", + stellarator_variables.f_w, + ) + po.ovarre( + stellarator.outfile, + "Magnetic stellarator_variables.shear (/m)", + "(shear)", + stellarator_variables.shear, + ) + po.ovarre(stellarator.outfile, "Divertor wetted area (m2)", "(A_eff)", a_eff) + po.ovarre( + stellarator.outfile, + "Wetted area fraction of total plate area", + "(fdivwet)", + stellarator_variables.fdivwet, + ) + po.ovarre(stellarator.outfile, "Divertor plate length (m)", "(L_d)", l_d) + po.ovarre(stellarator.outfile, "Divertor plate width (m)", "(L_w)", l_w) + po.ovarre(stellarator.outfile, "Flux channel broadening factor", "(F_x)", f_x) + po.ovarre(stellarator.outfile, "Power decay width (cm)", "(100*l_q)", 100.0e0 * l_q) + po.ovarre(stellarator.outfile, "Island width (m)", "(w_r)", w_r) + po.ovarre( + stellarator.outfile, + "Perp. distance from X-point to plate (m)", + "(Delta)", + Delta, + ) + po.ovarre( + stellarator.outfile, + "Peak heat load (MW/m2)", + "(pflux_div_heat_load_mw)", + divertor_variables.pflux_div_heat_load_mw, + ) diff --git a/process/stellarator/heating.py b/process/stellarator/heating.py new file mode 100644 index 0000000000..012015e340 --- /dev/null +++ b/process/stellarator/heating.py @@ -0,0 +1,224 @@ +import logging + +from process import process_output as po +from process.data_structure import ( + current_drive_variables, + heat_transport_variables, + physics_variables, + stellarator_variables, +) +from process.exceptions import ProcessValueError + +logger = logging.getLogger(__name__) + + +def st_heat(stellarator, f_output: bool): + """Routine to calculate the auxiliary heating power + in a stellarator + author: P J Knight, CCFE, Culham Science Centre + outfile : input integer : output file unit + iprint : input integer : switch for writing to output file (1=yes) + This routine calculates the auxiliary heating power for + a stellarator device. + AEA FUS 172: Physics Assessment for the European Reactor Study + """ + f_p_beam_injected_ions = None + if stellarator_variables.isthtr == 1: + current_drive_variables.p_hcd_ecrh_injected_total_mw = ( + current_drive_variables.p_hcd_primary_extra_heat_mw + ) + current_drive_variables.p_hcd_injected_ions_mw = 0 + current_drive_variables.p_hcd_injected_electrons_mw = ( + current_drive_variables.p_hcd_ecrh_injected_total_mw + ) + current_drive_variables.eta_hcd_primary_injector_wall_plug = ( + current_drive_variables.eta_ecrh_injector_wall_plug + ) + current_drive_variables.p_hcd_electric_total_mw = ( + current_drive_variables.p_hcd_injected_ions_mw + + current_drive_variables.p_hcd_injected_electrons_mw + ) / current_drive_variables.eta_hcd_primary_injector_wall_plug + + elif stellarator_variables.isthtr == 2: + current_drive_variables.p_hcd_lowhyb_injected_total_mw = ( + current_drive_variables.p_hcd_primary_extra_heat_mw + ) + current_drive_variables.p_hcd_injected_ions_mw = 0 + current_drive_variables.p_hcd_injected_electrons_mw = ( + current_drive_variables.p_hcd_lowhyb_injected_total_mw + ) + current_drive_variables.eta_hcd_primary_injector_wall_plug = ( + current_drive_variables.eta_lowhyb_injector_wall_plug + ) + heat_transport_variables.p_hcd_electric_total_mw = ( + current_drive_variables.p_hcd_injected_ions_mw + + current_drive_variables.p_hcd_injected_electrons_mw + ) / current_drive_variables.eta_hcd_primary_injector_wall_plug + + elif stellarator_variables.isthtr == 3: + ( + _effnbss, + f_p_beam_injected_ions, + current_drive_variables.f_p_beam_shine_through, + ) = stellarator.current_drive.culnbi() + current_drive_variables.p_hcd_beam_injected_total_mw = ( + current_drive_variables.p_hcd_primary_extra_heat_mw + * (1 - current_drive_variables.f_p_beam_orbit_loss) + ) + current_drive_variables.p_beam_orbit_loss_mw = ( + current_drive_variables.p_hcd_primary_extra_heat_mw + * current_drive_variables.f_p_beam_orbit_loss + ) + current_drive_variables.p_hcd_injected_ions_mw = ( + current_drive_variables.p_hcd_beam_injected_total_mw * f_p_beam_injected_ions + ) + current_drive_variables.p_hcd_injected_electrons_mw = ( + current_drive_variables.p_hcd_beam_injected_total_mw + * (1 - f_p_beam_injected_ions) + ) + current_drive_variables.eta_hcd_primary_injector_wall_plug = ( + current_drive_variables.eta_beam_injector_wall_plug + ) + current_drive_variables.p_hcd_electric_total_mw = ( + current_drive_variables.p_hcd_injected_ions_mw + + current_drive_variables.p_hcd_injected_electrons_mw + ) / current_drive_variables.eta_hcd_primary_injector_wall_plug + else: + logger.error(f"isthtr {stellarator_variables.isthtr}") + logger.error(f"isthtr type {type(stellarator_variables.isthtr)}") + raise ProcessValueError( + "Illegal value for isthtr", isthtr=stellarator_variables.isthtr + ) + + # Total injected power + + current_drive_variables.p_hcd_injected_total_mw = ( + current_drive_variables.p_hcd_injected_electrons_mw + + current_drive_variables.p_hcd_injected_ions_mw + ) + + # Calculate neutral beam current + + if abs(current_drive_variables.p_hcd_beam_injected_total_mw) > 1e-8: + current_drive_variables.c_beam_total = ( + 1e-3 + * (current_drive_variables.p_hcd_beam_injected_total_mw * 1e6) + / current_drive_variables.e_beam_kev + ) + else: + current_drive_variables.c_beam_total = 0 + + # Ratio of fusion to input (injection+ohmic) power + + if ( + abs( + current_drive_variables.p_hcd_injected_total_mw + + current_drive_variables.p_beam_orbit_loss_mw + + physics_variables.p_plasma_ohmic_mw + ) + < 1e-6 + ): + current_drive_variables.big_q_plasma = 1e18 + else: + current_drive_variables.big_q_plasma = physics_variables.p_fusion_total_mw / ( + current_drive_variables.p_hcd_injected_total_mw + + current_drive_variables.p_beam_orbit_loss_mw + + physics_variables.p_plasma_ohmic_mw + ) + + if f_output: + output(stellarator, f_p_beam_injected_ions) + + +def output(stellarator, f_p_beam_injected_ions=None): + po.oheadr(stellarator.outfile, "Auxiliary Heating System") + + if stellarator_variables.isthtr == 1: + po.ocmmnt(stellarator.outfile, "Electron Cyclotron Resonance Heating") + elif stellarator_variables.isthtr == 2: + po.ocmmnt(stellarator.outfile, "Lower Hybrid Heating") + elif stellarator_variables.isthtr == 3: + po.ocmmnt(stellarator.outfile, "Neutral Beam Injection Heating") + + if physics_variables.i_plasma_ignited == 1: + po.ocmmnt( + stellarator.outfile, + "Ignited plasma; injected power only used for start-up phase", + ) + + po.oblnkl(stellarator.outfile) + + po.ovarre( + stellarator.outfile, + "Auxiliary power supplied to plasma (MW)", + "(p_hcd_primary_extra_heat_mw)", + current_drive_variables.p_hcd_primary_extra_heat_mw, + ) + po.ovarre( + stellarator.outfile, + "Fusion gain factor Q", + "(big_q_plasma)", + current_drive_variables.big_q_plasma, + ) + + if abs(current_drive_variables.p_hcd_beam_injected_total_mw) > 1e-8: + po.ovarre( + stellarator.outfile, + "Neutral beam energy (KEV)", + "(enbeam)", + current_drive_variables.enbeam, + ) + po.ovarre( + stellarator.outfile, + "Neutral beam current (A)", + "(c_beam_total)", + current_drive_variables.c_beam_total, + ) + po.ovarre( + stellarator.outfile, + "Fraction of beam energy to ions", + "(f_p_beam_injected_ions)", + f_p_beam_injected_ions, + ) + po.ovarre( + stellarator.outfile, + "Neutral beam shine-through fraction", + "(f_p_beam_shine_through)", + current_drive_variables.f_p_beam_shine_through, + ) + po.ovarre( + stellarator.outfile, + "Neutral beam orbit loss power (MW)", + "(p_beam_orbit_loss_mw)", + current_drive_variables.p_beam_orbit_loss_mw, + ) + po.ovarre( + stellarator.outfile, + "Beam duct shielding thickness (m)", + "(dx_beam_shield)", + current_drive_variables.dx_beam_shield, + ) + po.ovarre( + stellarator.outfile, + "R injection tangent / R-major", + "(f_radius_beam_tangency_rmajor)", + current_drive_variables.f_radius_beam_tangency_rmajor, + ) + po.ovarre( + stellarator.outfile, + "Beam centreline tangency radius (m)", + "(radius_beam_tangency)", + current_drive_variables.radius_beam_tangency, + ) + po.ovarre( + stellarator.outfile, + "Maximum possible tangency radius (m)", + "(radius_beam_tangency_max)", + current_drive_variables.radius_beam_tangency_max, + ) + po.ovarre( + stellarator.outfile, + "Beam decay lengths to centre", + "(n_beam_decay_lengths_core)", + current_drive_variables.n_beam_decay_lengths_core, + ) diff --git a/process/stellarator/initialization.py b/process/stellarator/initialization.py new file mode 100644 index 0000000000..e96967398d --- /dev/null +++ b/process/stellarator/initialization.py @@ -0,0 +1,74 @@ +from process.data_structure import ( + build_variables, + current_drive_variables, + numerics, + pfcoil_variables, + physics_variables, + stellarator_variables, + times_variables, +) + + +def st_init(): + """Routine to initialise the variables relevant to stellarators + author: P J Knight, CCFE, Culham Science Centre + author: F Warmer, IPP Greifswald + + This routine initialises the variables relevant to stellarators. + Many of these may override the values set in routine + """ + if stellarator_variables.istell == 0: + return + + numerics.boundu[0] = 40.0 # allow higher aspect ratio + + # These lines switch off tokamak specifics (solenoid, pf coils, pulses etc.). + # Are they still up to date? (26/07/22 JL) + + # Build quantities + + build_variables.dr_cs = 0.0 + build_variables.iohcl = 0 + pfcoil_variables.f_z_cs_tf_internal = 0.0 + build_variables.dr_cs_tf_gap = 0.0 + build_variables.f_dr_tf_outboard_inboard = 1.0 + + # Physics quantities + + physics_variables.i_plasma_pedestal = 0 + physics_variables.beta_norm_max = 0.0 + physics_variables.kappa95 = 1.0 + physics_variables.triang = 0.0 + physics_variables.q95 = 1.03 + + # Turn off current drive + + current_drive_variables.i_hcd_calculations = 0 + + # Times for different phases + + times_variables.t_plant_pulse_coil_precharge = 0.0 + times_variables.t_plant_pulse_plasma_current_ramp_up = 0.0 + times_variables.t_plant_pulse_burn = 3.15576e7 # one year + times_variables.t_plant_pulse_plasma_current_ramp_down = 0.0 + times_variables.t_plant_pulse_plasma_present = ( + times_variables.t_plant_pulse_plasma_current_ramp_up + + times_variables.t_plant_pulse_fusion_ramp + + times_variables.t_plant_pulse_burn + + times_variables.t_plant_pulse_plasma_current_ramp_down + ) + times_variables.t_plant_pulse_no_burn = ( + times_variables.t_plant_pulse_coil_precharge + + times_variables.t_plant_pulse_plasma_current_ramp_up + + times_variables.t_plant_pulse_plasma_current_ramp_down + + times_variables.t_plant_pulse_dwell + + times_variables.t_plant_pulse_fusion_ramp + ) + times_variables.t_plant_pulse_total = ( + times_variables.t_plant_pulse_coil_precharge + + times_variables.t_plant_pulse_plasma_current_ramp_up + + times_variables.t_plant_pulse_fusion_ramp + + times_variables.t_plant_pulse_burn + + times_variables.t_plant_pulse_plasma_current_ramp_down + + times_variables.t_plant_pulse_dwell + ) diff --git a/process/stellarator/neoclassics.py b/process/stellarator/neoclassics.py new file mode 100644 index 0000000000..e6189a17b9 --- /dev/null +++ b/process/stellarator/neoclassics.py @@ -0,0 +1,793 @@ +import logging + +import numpy as np + +from process import constants +from process.data_structure import ( + impurity_radiation_module, + neoclassics_variables, + physics_variables, + stellarator_configuration, + stellarator_variables, +) +from process.stellarator.stellarator import KEV + +logger = logging.getLogger(__name__) + + +class Neoclassics: + @property + def no_roots(self): + return neoclassics_variables.roots.shape[0] + + def init_neoclassics(self, r_effin, eps_effin, iotain): + """Constructor of the neoclassics object from the effective radius, + epsilon effective and iota only. + """ + ( + neoclassics_variables.densities, + neoclassics_variables.temperatures, + neoclassics_variables.dr_densities, + neoclassics_variables.dr_temperatures, + ) = self.init_profile_values_from_PROCESS(r_effin) + neoclassics_variables.roots = np.array([ + 4.740718054080526184e-2, + 2.499239167531593919e-1, + 6.148334543927683749e-1, + 1.143195825666101451, + 1.836454554622572344, + 2.696521874557216147, + 3.725814507779509288, + 4.927293765849881879, + 6.304515590965073635, + 7.861693293370260349, + 9.603775985479263255, + 1.153654659795613924e1, + 1.366674469306423489e1, + 1.600222118898106771e1, + 1.855213484014315029e1, + 2.132720432178312819e1, + 2.434003576453269346e1, + 2.760555479678096091e1, + 3.114158670111123683e1, + 3.496965200824907072e1, + 3.911608494906788991e1, + 4.361365290848483056e1, + 4.850398616380419980e1, + 5.384138540650750571e1, + 5.969912185923549686e1, + 6.618061779443848991e1, + 7.344123859555988076e1, + 8.173681050672767867e1, + 9.155646652253683726e1, + 1.041575244310588886e2, + ]) + neoclassics_variables.weights = np.array([ + 1.160440860204388913e-1, + 2.208511247506771413e-1, + 2.413998275878537214e-1, + 1.946367684464170855e-1, + 1.237284159668764899e-1, + 6.367878036898660943e-2, + 2.686047527337972682e-2, + 9.338070881603925677e-3, + 2.680696891336819664e-3, + 6.351291219408556439e-4, + 1.239074599068830081e-4, + 1.982878843895233056e-5, + 2.589350929131392509e-6, + 2.740942840536013206e-7, + 2.332831165025738197e-8, + 1.580745574778327984e-9, + 8.427479123056716393e-11, + 3.485161234907855443e-12, + 1.099018059753451500e-13, + 2.588312664959080167e-15, + 4.437838059840028968e-17, + 5.365918308212045344e-19, + 4.393946892291604451e-21, + 2.311409794388543236e-23, + 7.274588498292248063e-26, + 1.239149701448267877e-28, + 9.832375083105887477e-32, + 2.842323553402700938e-35, + 1.878608031749515392e-39, + 8.745980440465011553e-45, + ]) + + neoclassics_variables.kt = self.neoclassics_calc_KT() + neoclassics_variables.nu = self.neoclassics_calc_nu() + neoclassics_variables.nu_star = self.neoclassics_calc_nu_star() + neoclassics_variables.nu_star_averaged = self.neoclassics_calc_nu_star_fromT( + iotain + ) + neoclassics_variables.vd = self.neoclassics_calc_vd() + + neoclassics_variables.d11_plateau = self.neoclassics_calc_D11_plateau() + + neoclassics_variables.d11_mono = self.neoclassics_calc_d11_mono( + eps_effin + ) # for using epseff + + neoclassics_variables.d111 = self.calc_integrated_radial_transport_coeffs( + index=1 + ) + neoclassics_variables.d112 = self.calc_integrated_radial_transport_coeffs( + index=2 + ) + neoclassics_variables.d113 = self.calc_integrated_radial_transport_coeffs( + index=3 + ) + + neoclassics_variables.gamma_flux = self.neoclassics_calc_gamma_flux( + neoclassics_variables.densities, + neoclassics_variables.temperatures, + neoclassics_variables.dr_densities, + neoclassics_variables.dr_temperatures, + ) + neoclassics_variables.q_flux = self.neoclassics_calc_q_flux() + + def init_profile_values_from_PROCESS(self, rho): + """Initializes the profile_values object from PROCESS' parabolic profiles""" + tempe = ( + physics_variables.temp_plasma_electron_on_axis_kev + * (1 - rho**2) ** physics_variables.alphat + * KEV + ) + tempT = ( + physics_variables.temp_plasma_ion_on_axis_kev + * (1 - rho**2) ** physics_variables.alphat + * KEV + ) + tempD = ( + physics_variables.temp_plasma_ion_on_axis_kev + * (1 - rho**2) ** physics_variables.alphat + * KEV + ) + tempa = ( + physics_variables.temp_plasma_ion_on_axis_kev + * (1 - rho**2) ** physics_variables.alphat + * KEV + ) + + dense = ( + physics_variables.nd_plasma_electron_on_axis + * (1 - rho**2) ** physics_variables.alphan + ) + densT = ( + (1 - physics_variables.f_plasma_fuel_deuterium) + * physics_variables.nd_plasma_ions_on_axis + * (1 - rho**2) ** physics_variables.alphan + ) + densD = ( + physics_variables.f_plasma_fuel_deuterium + * physics_variables.nd_plasma_ions_on_axis + * (1 - rho**2) ** physics_variables.alphan + ) + densa = ( + physics_variables.nd_plasma_alphas_vol_avg + * (1 + physics_variables.alphan) + * (1 - rho**2) ** physics_variables.alphan + ) + + # Derivatives in real space + dr_tempe = ( + -2.0 + * 1.0 + / physics_variables.rminor + * physics_variables.temp_plasma_electron_on_axis_kev + * rho + * (1.0 - rho**2) ** (physics_variables.alphat - 1.0) + * physics_variables.alphat + * KEV + ) + dr_tempT = ( + -2.0 + * 1.0 + / physics_variables.rminor + * physics_variables.temp_plasma_ion_on_axis_kev + * rho + * (1.0 - rho**2) ** (physics_variables.alphat - 1.0) + * physics_variables.alphat + * KEV + ) + dr_tempD = ( + -2.0 + * 1.0 + / physics_variables.rminor + * physics_variables.temp_plasma_ion_on_axis_kev + * rho + * (1.0 - rho**2) ** (physics_variables.alphat - 1.0) + * physics_variables.alphat + * KEV + ) + dr_tempa = ( + -2.0 + * 1.0 + / physics_variables.rminor + * physics_variables.temp_plasma_ion_on_axis_kev + * rho + * (1.0 - rho**2) ** (physics_variables.alphat - 1.0) + * physics_variables.alphat + * KEV + ) + + dr_dense = ( + -2.0 + * 1.0 + / physics_variables.rminor + * rho + * physics_variables.nd_plasma_electron_on_axis + * (1.0 - rho**2) ** (physics_variables.alphan - 1.0) + * physics_variables.alphan + ) + dr_densT = ( + -2.0 + * 1.0 + / physics_variables.rminor + * rho + * (1 - physics_variables.f_plasma_fuel_deuterium) + * physics_variables.nd_plasma_ions_on_axis + * (1.0 - rho**2) ** (physics_variables.alphan - 1.0) + * physics_variables.alphan + ) + dr_densD = ( + -2.0 + * 1.0 + / physics_variables.rminor + * rho + * physics_variables.f_plasma_fuel_deuterium + * physics_variables.nd_plasma_ions_on_axis + * (1.0 - rho**2) ** (physics_variables.alphan - 1.0) + * physics_variables.alphan + ) + dr_densa = ( + -2.0 + * 1.0 + / physics_variables.rminor + * rho + * physics_variables.nd_plasma_alphas_vol_avg + * (1 + physics_variables.alphan) + * (1.0 - rho**2) ** (physics_variables.alphan - 1.0) + * physics_variables.alphan + ) + + dens = np.array([dense, densD, densT, densa]) + temp = np.array([tempe, tempD, tempT, tempa]) + dr_dens = np.array([dr_dense, dr_densD, dr_densT, dr_densa]) + dr_temp = np.array([dr_tempe, dr_tempD, dr_tempT, dr_tempa]) + + return dens, temp, dr_dens, dr_temp + + def calc_neoclassics(self): + if stellarator_configuration.stella_config_epseff < 0: + logger.error( + f"epseff value lower than 0: {stellarator_configuration.stella_config_epseff}" + ) + self.init_neoclassics( + 0.6, + stellarator_configuration.stella_config_epseff, + stellarator_variables.iotabar, + ) + + q_PROCESS = ( + ( + physics_variables.f_p_alpha_plasma_deposited + * physics_variables.pden_alpha_total_mw + - physics_variables.pden_plasma_core_rad_mw + ) + * physics_variables.vol_plasma + / physics_variables.a_plasma_surface + * impurity_radiation_module.radius_plasma_core_norm + ) + q_PROCESS_r1 = ( + ( + physics_variables.f_p_alpha_plasma_deposited + * physics_variables.pden_alpha_total_mw + - physics_variables.pden_plasma_core_rad_mw + ) + * physics_variables.vol_plasma + / physics_variables.a_plasma_surface + ) + + q_neo = sum(neoclassics_variables.q_flux * 1e-6) + gamma_neo = sum( + neoclassics_variables.gamma_flux * neoclassics_variables.temperatures * 1e-6 + ) + + total_q_neo = sum( + neoclassics_variables.q_flux * 1e-6 + + neoclassics_variables.gamma_flux + * neoclassics_variables.temperatures + * 1e-6 + ) + + total_q_neo_e = ( + 2 + * 2 + * ( + neoclassics_variables.q_flux[0] * 1e-6 + + neoclassics_variables.gamma_flux[0] + * neoclassics_variables.temperatures[0] + * 1e-6 + ) + ) + + q_neo_e = neoclassics_variables.q_flux[0] * 1e-6 + q_neo_D = neoclassics_variables.q_flux[1] * 1e-6 + q_neo_a = neoclassics_variables.q_flux[3] * 1e-6 + q_neo_T = neoclassics_variables.q_flux[2] * 1e-6 + + g_neo_e = ( + neoclassics_variables.gamma_flux[0] + * 1e-6 + * neoclassics_variables.temperatures[0] + ) + g_neo_D = ( + neoclassics_variables.gamma_flux[1] + * 1e-6 + * neoclassics_variables.temperatures[1] + ) + g_neo_a = ( + neoclassics_variables.gamma_flux[3] + * 1e-6 + * neoclassics_variables.temperatures[3] + ) + g_neo_T = ( + neoclassics_variables.gamma_flux[2] + * 1e-6 + * neoclassics_variables.temperatures[2] + ) + + dndt_neo_e = neoclassics_variables.gamma_flux[0] + dndt_neo_D = neoclassics_variables.gamma_flux[1] + dndt_neo_a = neoclassics_variables.gamma_flux[3] + dndt_neo_T = neoclassics_variables.gamma_flux[2] + + dndt_neo_fuel = ( + (dndt_neo_D + dndt_neo_T) + * physics_variables.a_plasma_surface + * impurity_radiation_module.radius_plasma_core_norm + ) + dmdt_neo_fuel = ( + dndt_neo_fuel * physics_variables.m_fuel_amu * constants.PROTON_MASS * 1.0e6 + ) # mg + dmdt_neo_fuel_from_e = ( + 4 + * dndt_neo_e + * physics_variables.a_plasma_surface + * impurity_radiation_module.radius_plasma_core_norm + * physics_variables.m_fuel_amu + * constants.PROTON_MASS + * 1.0e6 + ) # kg + + chi_neo_e = -( + neoclassics_variables.q_flux[0] + + neoclassics_variables.gamma_flux[0] * neoclassics_variables.temperatures[0] + ) / ( + neoclassics_variables.densities[0] * neoclassics_variables.dr_temperatures[0] + + neoclassics_variables.temperatures[0] + * neoclassics_variables.dr_densities[0] + ) + + chi_PROCESS_e = self.st_calc_eff_chi() + + nu_star_e = neoclassics_variables.nu_star_averaged[0] + nu_star_d = neoclassics_variables.nu_star_averaged[1] + nu_star_T = neoclassics_variables.nu_star_averaged[2] + nu_star_He = neoclassics_variables.nu_star_averaged[3] + + return ( + q_PROCESS, + q_PROCESS_r1, + q_neo, + gamma_neo, + total_q_neo, + total_q_neo_e, + q_neo_e, + q_neo_D, + q_neo_a, + q_neo_T, + g_neo_e, + g_neo_D, + g_neo_a, + g_neo_T, + dndt_neo_e, + dndt_neo_D, + dndt_neo_a, + dndt_neo_T, + dndt_neo_fuel, + dmdt_neo_fuel, + dmdt_neo_fuel_from_e, + chi_neo_e, + chi_PROCESS_e, + nu_star_e, + nu_star_d, + nu_star_T, + nu_star_He, + ) + + def neoclassics_calc_KT(self): + """Calculates the energy on the given grid + which is given by the gauss laguerre roots. + """ + k = np.repeat((neoclassics_variables.roots / KEV)[:, np.newaxis], 4, axis=1) + + return (k * neoclassics_variables.temperatures).T + + def neoclassics_calc_nu(self): + """Calculates the collision frequency""" + mass = np.array([ + constants.ELECTRON_MASS, + constants.PROTON_MASS * 2.0, + constants.PROTON_MASS * 3.0, + constants.PROTON_MASS * 4.0, + ]) + z = np.array([-1.0, 1.0, 1.0, 2.0]) * constants.ELECTRON_CHARGE + + # transform the temperature back in eV + # Formula from L. Spitzer.Physics of fully ionized gases. Interscience, New York, 1962 + lnlambda = ( + 32.2 + - 1.15 * np.log10(neoclassics_variables.densities[0]) + + 2.3 + * np.log10(neoclassics_variables.temperatures[0] / constants.ELECTRON_CHARGE) + ) + + neoclassics_calc_nu = np.zeros((4, self.no_roots), order="F") + + for j in range(4): + for i in range(self.no_roots): + x = neoclassics_variables.roots[i] + for k in range(4): + xk = ( + (mass[k] / mass[j]) + * ( + neoclassics_variables.temperatures[j] + / neoclassics_variables.temperatures[k] + ) + * x + ) + expxk = np.exp(-xk) + t = 1.0 / (1.0 + 0.3275911 * np.sqrt(xk)) + erfn = ( + 1.0 + - t + * ( + 0.254829592 + + t + * ( + -0.284496736 + + t + * (1.421413741 + t * (-1.453152027 + t * 1.061405429)) + ) + ) + * expxk + ) + phixmgx = (1.0 - 0.5 / xk) * erfn + expxk / np.sqrt(np.pi * xk) + v = np.sqrt( + 2.0 * x * neoclassics_variables.temperatures[j] / mass[j] + ) + neoclassics_calc_nu[j, i] = neoclassics_calc_nu[ + j, i + ] + neoclassics_variables.densities[k] * ( + z[j] * z[k] + ) ** 2 * lnlambda * phixmgx / ( + 4.0 * np.pi * constants.EPSILON0**2 * mass[j] ** 2 * v**3 + ) + + return neoclassics_calc_nu + + def neoclassics_calc_nu_star(self): + """Calculates the normalized collision frequency""" + + mass = np.array([ + constants.ELECTRON_MASS, + constants.PROTON_MASS * 2.0, + constants.PROTON_MASS * 3.0, + constants.PROTON_MASS * 4.0, + ]) + + v = np.empty((4, self.no_roots)) + v[0, :] = constants.SPEED_LIGHT * np.sqrt( + 1.0 + - (neoclassics_variables.kt[0, :] / (mass[0] * constants.SPEED_LIGHT**2) + 1) + ** (-1) + ) + v[1, :] = constants.SPEED_LIGHT * np.sqrt( + 1.0 + - (neoclassics_variables.kt[1, :] / (mass[1] * constants.SPEED_LIGHT**2) + 1) + ** (-1) + ) + v[2, :] = constants.SPEED_LIGHT * np.sqrt( + 1.0 + - (neoclassics_variables.kt[2, :] / (mass[2] * constants.SPEED_LIGHT**2) + 1) + ** (-1) + ) + v[3, :] = constants.SPEED_LIGHT * np.sqrt( + 1.0 + - (neoclassics_variables.kt[3, :] / (mass[3] * constants.SPEED_LIGHT**2) + 1) + ** (-1) + ) + + return ( + physics_variables.rmajor + * neoclassics_variables.nu + / (neoclassics_variables.iota * v) + ) + + def neoclassics_calc_nu_star_fromT(self, iota): + """Calculates the collision frequency""" + temp = ( + np.array([ + physics_variables.temp_plasma_electron_vol_avg_kev, + physics_variables.temp_plasma_ion_vol_avg_kev, + physics_variables.temp_plasma_ion_vol_avg_kev, + physics_variables.temp_plasma_ion_vol_avg_kev, + ]) + * KEV + ) + density = np.array([ + physics_variables.nd_plasma_electrons_vol_avg, + physics_variables.nd_plasma_fuel_ions_vol_avg + * physics_variables.f_plasma_fuel_deuterium, + physics_variables.nd_plasma_fuel_ions_vol_avg + * (1 - physics_variables.f_plasma_fuel_deuterium), + physics_variables.nd_plasma_alphas_vol_avg, + ]) + + mass = np.array([ + constants.ELECTRON_MASS, + constants.PROTON_MASS * 2.0, + constants.PROTON_MASS * 3.0, + constants.PROTON_MASS * 4.0, + ]) + z = np.array([-1.0, 1.0, 1.0, 2.0]) * constants.ELECTRON_CHARGE + + # transform the temperature back in eV + # Formula from L. Spitzer.Physics of fully ionized gases. Interscience, New York, 1962 + lnlambda = ( + 32.2 + - 1.15 * np.log10(density[0]) + + 2.3 * np.log10(temp[0] / constants.ELECTRON_CHARGE) + ) + + neoclassics_calc_nu_star_fromT = np.zeros((4,)) + + for j in range(4): + v = np.sqrt(2.0 * temp[j] / mass[j]) + for k in range(4): + xk = (mass[k] / mass[j]) * (temp[j] / temp[k]) + + expxk = 0.0 + if xk < 200.0: + expxk = np.exp(-xk) + + t = 1.0 / (1.0 + 0.3275911 * np.sqrt(xk)) + erfn = ( + 1.0 + - t + * ( + 0.254829592 + + t + * ( + -0.284496736 + + t * (1.421413741 + t * (-1.453152027 + t * 1.061405429)) + ) + ) + * expxk + ) + phixmgx = (1.0 - 0.5 / xk) * erfn + expxk / np.sqrt(np.pi * xk) + neoclassics_calc_nu_star_fromT[j] = ( + neoclassics_calc_nu_star_fromT[j] + + density[k] + * (z[j] * z[k]) ** 2 + * lnlambda + * phixmgx + / (4.0 * np.pi * constants.EPSILON0**2 * mass[j] ** 2 * v**4) + * physics_variables.rmajor + / iota + ) + return neoclassics_calc_nu_star_fromT + + def neoclassics_calc_vd(self): + vde = ( + neoclassics_variables.roots + * neoclassics_variables.temperatures[0] + / ( + constants.ELECTRON_CHARGE + * physics_variables.rmajor + * physics_variables.b_plasma_toroidal_on_axis + ) + ) + vdD = ( + neoclassics_variables.roots + * neoclassics_variables.temperatures[1] + / ( + constants.ELECTRON_CHARGE + * physics_variables.rmajor + * physics_variables.b_plasma_toroidal_on_axis + ) + ) + vdT = ( + neoclassics_variables.roots + * neoclassics_variables.temperatures[2] + / ( + constants.ELECTRON_CHARGE + * physics_variables.rmajor + * physics_variables.b_plasma_toroidal_on_axis + ) + ) + vda = ( + neoclassics_variables.roots + * neoclassics_variables.temperatures[3] + / ( + 2.0 + * constants.ELECTRON_CHARGE + * physics_variables.rmajor + * physics_variables.b_plasma_toroidal_on_axis + ) + ) + + vd = np.empty((4, self.no_roots)) + + vd[0, :] = vde + vd[1, :] = vdD + vd[2, :] = vdT + vd[3, :] = vda + + return vd + + def neoclassics_calc_D11_plateau(self): + """Calculates the plateau transport coefficients (D11_star sometimes)""" + mass = np.array([ + constants.ELECTRON_MASS, + constants.PROTON_MASS * 2.0, + constants.PROTON_MASS * 3.0, + constants.PROTON_MASS * 4.0, + ]) + + v = np.empty((4, self.no_roots)) + v[0, :] = constants.SPEED_LIGHT * np.sqrt( + 1.0 + - (neoclassics_variables.kt[0, :] / (mass[0] * constants.SPEED_LIGHT**2) + 1) + ** (-1) + ) + v[1, :] = constants.SPEED_LIGHT * np.sqrt( + 1.0 + - (neoclassics_variables.kt[1, :] / (mass[1] * constants.SPEED_LIGHT**2) + 1) + ** (-1) + ) + v[2, :] = constants.SPEED_LIGHT * np.sqrt( + 1.0 + - (neoclassics_variables.kt[2, :] / (mass[2] * constants.SPEED_LIGHT**2) + 1) + ** (-1) + ) + v[3, :] = constants.SPEED_LIGHT * np.sqrt( + 1.0 + - (neoclassics_variables.kt[3, :] / (mass[3] * constants.SPEED_LIGHT**2) + 1) + ** (-1) + ) + + return ( + np.pi + / 4.0 + * neoclassics_variables.vd**2 + * physics_variables.rmajor + / neoclassics_variables.iota + / v + ) + + def neoclassics_calc_d11_mono(self, eps_eff): + """Calculates the monoenergetic radial transport coefficients + using epsilon effective + """ + return ( + 4.0 + / (9.0 * np.pi) + * (2.0 * eps_eff) ** (3.0 / 2.0) + * neoclassics_variables.vd**2 + / neoclassics_variables.nu + ) + + def calc_integrated_radial_transport_coeffs(self, index: int): + """Calculates the integrated radial transport coefficients (index `index`) + It uses Gauss laguerre integration + https://en.wikipedia.org/wiki/Gauss%E2%80%93Laguerre_quadrature + """ + return np.sum( + 2.0 + / np.sqrt(np.pi) + * neoclassics_variables.d11_mono + * neoclassics_variables.roots ** (index - 0.5) + * neoclassics_variables.weights, + axis=1, + ) + + def neoclassics_calc_gamma_flux( + self, densities, temperatures, dr_densities, dr_temperatures + ): + """Calculates the Energy flux by neoclassical particle transport""" + + z = np.array([-1.0, 1.0, 1.0, 2.0]) + + return ( + -densities + * neoclassics_variables.d111 + * ( + (dr_densities / densities - z * neoclassics_variables.er / temperatures) + + (neoclassics_variables.d112 / neoclassics_variables.d111 - 3.0 / 2.0) + * dr_temperatures + / temperatures + ) + ) + + def neoclassics_calc_q_flux(self): + """Calculates the Energy flux by neoclassicsal energy transport""" + + z = np.array([-1.0, 1.0, 1.0, 2.0]) + + return ( + -neoclassics_variables.densities + * neoclassics_variables.temperatures + * neoclassics_variables.d112 + * ( + ( + neoclassics_variables.dr_densities / neoclassics_variables.densities + - z * neoclassics_variables.er / neoclassics_variables.temperatures + ) + + (neoclassics_variables.d113 / neoclassics_variables.d112 - 3.0 / 2.0) + * neoclassics_variables.dr_temperatures + / neoclassics_variables.temperatures + ) + ) + + def st_calc_eff_chi(self): + volscaling = ( + physics_variables.vol_plasma + * stellarator_variables.f_st_rmajor + * ( + impurity_radiation_module.radius_plasma_core_norm + * physics_variables.rminor + / stellarator_configuration.stella_config_rminor_ref + ) + ** 2 + ) + surfacescaling = ( + physics_variables.a_plasma_surface + * stellarator_variables.f_st_rmajor + * ( + impurity_radiation_module.radius_plasma_core_norm + * physics_variables.rminor + / stellarator_configuration.stella_config_rminor_ref + ) + ) + + nominator = ( + physics_variables.f_p_alpha_plasma_deposited + * physics_variables.pden_alpha_total_mw + - physics_variables.pden_plasma_core_rad_mw + ) * volscaling + + # in fortran there was a 0*alphan term which I have removed for obvious reasons + # the following comment seems to describe this? + # "include alphan if chi should be incorporate density gradients too" + # but the history can be consulted if required (23/11/22 TN) + denominator = ( + ( + 3 + * physics_variables.nd_plasma_electron_on_axis + * constants.ELECTRON_CHARGE + * physics_variables.temp_plasma_electron_on_axis_kev + * 1e3 + * physics_variables.alphat + * impurity_radiation_module.radius_plasma_core_norm + * (1 - impurity_radiation_module.radius_plasma_core_norm**2) + ** (physics_variables.alphan + physics_variables.alphat - 1) + ) + * surfacescaling + * 1e-6 + ) + + return nominator / denominator diff --git a/process/stellarator_config.py b/process/stellarator/preset_config.py similarity index 100% rename from process/stellarator_config.py rename to process/stellarator/preset_config.py diff --git a/process/stellarator/stellarator.py b/process/stellarator/stellarator.py new file mode 100644 index 0000000000..9fd249c019 --- /dev/null +++ b/process/stellarator/stellarator.py @@ -0,0 +1,2513 @@ +import logging +from pathlib import Path + +import numpy as np + +import process.fusion_reactions as reactions +import process.physics_functions as physics_funcs +from process import constants +from process import process_output as po +from process.coolprop_interface import FluidProperties +from process.data_structure import ( + build_variables, + constraint_variables, + cost_variables, + current_drive_variables, + divertor_variables, + fwbs_variables, + global_variables, + heat_transport_variables, + numerics, + physics_variables, + stellarator_configuration, + stellarator_variables, + structure_variables, + tfcoil_variables, +) +from process.exceptions import ProcessValueError +from process.physics import Physics, rether +from process.stellarator.build import st_build +from process.stellarator.coils.calculate import st_coil +from process.stellarator.denisty_limits import power_at_ignition_point, st_denisty_limits +from process.stellarator.divertor import st_div +from process.stellarator.heating import st_heat +from process.stellarator.preset_config import load_stellarator_config + +logger = logging.getLogger(__name__) + +# NOTE: a different value of electron_charge was used in the original implementation +# making the post-Python results slightly different. As a result, there is a +# relative tolerance on the neoclassics tests of 1e-3 +KEV = 1e3 * constants.ELECTRON_CHARGE # Kiloelectron-volt (keV) + + +class Stellarator: + """Module containing stellarator routines + author: P J Knight, CCFE, Culham Science Centre + N/A + This module contains routines for calculating the + parameters of the first wall, blanket and shield components + of a fusion power plant. + + """ + + def __init__( + self, + availability, + vacuum, + buildings, + costs, + power, + plasma_profile, + hcpb, + current_drive, + physics: Physics, + neoclassics, + ) -> None: + """Initialises the Stellarator model's variables + + :param availability: a pointer to the availability model, allowing use of availability's variables/methods + :type availability: process.availability.Availability + :param buildings: a pointer to the buildings model, allowing use of buildings's variables/methods + :type buildings: process.buildings.Buildings + :param Vacuum: a pointer to the vacuum model, allowing use of vacuum's variables/methods + :type Vacuum: process.vacuum.Vacuum + :param costs: a pointer to the costs model, allowing use of costs' variables/methods + :type costs: process.costs.Costs + :param plasma_profile: a pointer to the plasma_profile model, allowing use of plasma_profile's variables/methods + :type plasma_profile: process.plasma_profile.PlasmaProfile + :param hcpb: a pointer to the ccfe_hcpb model, allowing use of ccfe_hcpb's variables/methods + :type hcpb: process.hcpb.CCFE_HCPB + :param current_drive: a pointer to the CurrentDrive model, allowing use of CurrentDrives's variables/methods + :type current_drive: process.current_drive.CurrentDrive + :param physics: a pointer to the Physics model, allowing use of Physics's variables/methods + :type physics: process.physics.Physics + :param neoclassics: a pointer to the Neoclassics model, allowing use of neoclassics's variables/methods + :type neoclassics: process.stellarator.Neoclassics + """ + + self.outfile: int = constants.NOUT + self.first_call_stfwbs = True + + self.availability = availability + self.buildings = buildings + self.vacuum = vacuum + self.costs = costs + self.power = power + self.plasma_profile = plasma_profile + self.hcpb = hcpb + self.current_drive = current_drive + self.physics = physics + self.neoclassics = neoclassics + + def run(self, output: bool): + """Routine to call the physics and engineering modules + relevant to stellarators + author: P J Knight, CCFE, Culham Science Centre + author: F Warmer, IPP Greifswald + + This routine is the caller for the stellarator models. + + :param output: indicate whether output should be written to the output file, or not + :type output: boolean + """ + + if output: + self.costs.run() + self.costs.output() + self.availability.run(output=True) + self.physics.calculate_effective_charge_ionisation_profiles() + self.physics.outplas() + st_heat(self, True) + self.st_phys(True) + st_denisty_limits(self, True) + + # Change in density limit can result in changed dene? + # A second call of st_phys is used to make sure it is consitent. + # st_phys and denisty limits should be integarted to avoid this double call. + # Problem was probably bigger in the older version + + self.st_phys(False) + + st_div(self, True) + st_build(self, True) + st_coil(self, True) + self.st_strc(True) + self.st_fwbs(True) + + self.power.tfpwr(output=True) + self.buildings.run(output=True) + self.vacuum.run(output=True) + self.power.acpow(output=True) + self.power.output_plant_electric_powers() + + return + + self.st_new_config() + self.st_geom() + self.st_phys(False) + st_denisty_limits(self, False) + st_coil(self, False) + st_build(self, False) + self.st_strc(False) + self.st_fwbs(False) + st_div(self, False) + + self.power.tfpwr(output=False) + self.power.component_thermal_powers() + self.power.calculate_cryo_loads() + self.buildings.run(output=False) + self.vacuum.run(output=False) + self.power.acpow(output=False) + self.power.plant_electric_production() + # TODO: should availability.run be called + # rather than availability.avail? + self.availability.avail(output=False) + self.costs.run() + + if 91 in numerics.icc: + # This call is comparably time consuming.. + # If the respective constraint equation is not called, do not set the values + ( + stellarator_variables.powerht_constraint, + stellarator_variables.powerscaling_constraint, + ) = power_at_ignition_point( + stellarator_variables.max_gyrotron_frequency, + stellarator_variables.te0_ecrh_achievable, + ) + + stellarator_variables.first_call = False + + def st_new_config(self): + """author: J Lion, IPP Greifswald + Routine to initialise the stellarator configuration + + Routine to initialise the stellarator configuration. + This routine is called right before the calculation and could + in principle overwrite variables from the input file. + It overwrites rminor with rmajor and aspect ratio e.g. + + To clarify the coils scaling factor: + Coil aspect ratio factor can be described with the reversed equation (so if we would know r_coil_minor) + stellarator_variables.f_coil_aspect = ( + (physics_variables.rmajor / stellarator_variables.r_coil_minor) / + (stellarator_configuration.stella_config_rmajor_ref / + stellarator_configuration.stella_config_coil_rminor) + ) + """ + + load_stellarator_config( + stellarator_variables.istell, + Path(f"{global_variables.output_prefix}stella_conf.json"), + ) + + # If physics_variables.aspect ratio is not in numerics.ixc set it to default value + # Or when you call it the first time + if 1 not in numerics.ixc: + physics_variables.aspect = stellarator_configuration.stella_config_aspect_ref + + # Set the physics_variables.rminor radius as result here. + physics_variables.rminor = physics_variables.rmajor / physics_variables.aspect + physics_variables.eps = 1.0e0 / physics_variables.aspect + + tfcoil_variables.n_tf_coils = ( + stellarator_configuration.stella_config_coilspermodule + * stellarator_configuration.stella_config_symmetry + ) # This overwrites tfcoil_variables.n_tf_coils in input file. + + stellarator_variables.f_st_rmajor = ( + physics_variables.rmajor / stellarator_configuration.stella_config_rmajor_ref + ) # Size scaling factor with respect to the reference calculation + stellarator_variables.f_st_rminor = ( + physics_variables.rminor / stellarator_configuration.stella_config_rminor_ref + ) # Size scaling factor with respect to the reference calculation + + stellarator_variables.f_st_aspect = ( + physics_variables.aspect / stellarator_configuration.stella_config_aspect_ref + ) + stellarator_variables.f_st_n_coils = tfcoil_variables.n_tf_coils / ( + stellarator_configuration.stella_config_coilspermodule + * stellarator_configuration.stella_config_symmetry + ) # Coil number factor + stellarator_variables.f_st_b = ( + physics_variables.b_plasma_toroidal_on_axis + / stellarator_configuration.stella_config_bt_ref + ) # B-field scaling factor + + # Coil aspect ratio factor to the reference calculation (we use it to scale the coil minor radius) + stellarator_variables.f_coil_aspect = stellarator_variables.f_st_coil_aspect + + # Coil major radius, scaled with respect to the reference calculation + stellarator_variables.r_coil_major = ( + stellarator_configuration.stella_config_coil_rmajor + * stellarator_variables.f_st_rmajor + ) + # Coil minor radius, scaled with respect to the reference calculation + stellarator_variables.r_coil_minor = ( + stellarator_configuration.stella_config_coil_rminor + * stellarator_variables.f_st_rmajor + / stellarator_variables.f_coil_aspect + ) + + stellarator_variables.f_coil_shape = ( + stellarator_configuration.stella_config_min_plasma_coil_distance + + stellarator_configuration.stella_config_rminor_ref + ) / stellarator_configuration.stella_config_coil_rminor + + def st_geom(self): + """ + author: J Lion, IPP Greifswald + Routine to calculate the plasma volume and surface area for + a stellarator using precalculated effective values + + This routine calculates the plasma volume and surface area for + a stellarator configuration. + It is simple scaling based on a Fourier representation based on + that described in Geiger documentation. + + J. Geiger, IPP Greifswald internal document: 'Darstellung von + ineinandergeschachtelten toroidal geschlossenen Flaechen mit + Fourierkoeffizienten' ('Representation of nested, closed + surfaces with Fourier coefficients') + """ + physics_variables.vol_plasma = ( + stellarator_variables.f_st_rmajor + * stellarator_variables.f_st_rminor**2 + * stellarator_configuration.stella_config_vol_plasma + ) + + # Plasma surface scaled from effective parameter: + physics_variables.a_plasma_surface = ( + stellarator_variables.f_st_rmajor + * stellarator_variables.f_st_rminor + * stellarator_configuration.stella_config_plasma_surface + ) + + # Plasma cross section area. Approximated + physics_variables.a_plasma_poloidal = ( + np.pi * physics_variables.rminor * physics_variables.rminor + ) # average, could be calculated for every toroidal angle if desired + + # physics_variables.a_plasma_surface_outboard is retained only for obsolescent fispact calculation... + + # Cross-sectional area, averaged over toroidal angle + physics_variables.a_plasma_surface_outboard = ( + 0.5e0 * physics_variables.a_plasma_surface + ) # Used only in the divertor model; approximate as for tokamaks + + def st_strc(self, output): + """ + Routine to calculate the structural masses for a stellarator + author: P J Knight, CCFE, Culham Science Centre + outfile : input integer : output file unit + iprint : input integer : switch for writing to output file (1=yes) + This routine calculates the structural masses for a stellarator. + This is the stellarator version of routine + STRUCT. In practice, many of the masses + are simply set to zero to avoid double-counting of structural + components that are specified differently for tokamaks. + """ + structure_variables.fncmass = 0.0e0 + + # Reactor core gravity support mass + structure_variables.gsmass = 0.0e0 # ? Not sure about this. + + # This is the previous scaling law for intercoil structure + # We keep is here as a reference to the new model, which + # we do not really trust yet. + # Mass of support structure (includes casing) (tonnes) + # Scaling for required structure mass (Steel) from: + # F.C. Moon, J. Appl. Phys. 53(12) (1982) 9112 + # + # Values based on regression analysis by Greifswald, March 2014 + m_struc = ( + 1.3483e0 + * (1000.0e0 * tfcoil_variables.e_tf_magnetic_stored_total_gj) ** 0.7821e0 + ) + msupstr = 1000.0e0 * m_struc # kg + + ################################################################ + # Intercoil support structure calculation: + # Calculate the intercoil bolted plates structure from the coil surface + + intercoil_surface = ( + stellarator_configuration.stella_config_coilsurface + * stellarator_variables.f_st_rmajor + * ( + stellarator_variables.r_coil_minor + / stellarator_configuration.stella_config_coil_rminor + ) + - tfcoil_variables.dx_tf_inboard_out_toroidal + * tfcoil_variables.len_tf_coil + * tfcoil_variables.n_tf_coils + ) + + # This 0.18 m is an effective thickness which is scaled with empirial 1.5 law. 5.6 T is reference point of Helias + # The thickness 0.18m was obtained as a measured value from Schauer, F. and Bykov, V. design of Helias 5-B. (Nucl Fus. 2013) + structure_variables.aintmass = ( + 0.18e0 + * (physics_variables.b_plasma_toroidal_on_axis / 5.6) ** 2 + * intercoil_surface + * fwbs_variables.den_steel + ) + + structure_variables.clgsmass = ( + 0.2e0 * structure_variables.aintmass + ) # Very simple approximation for the gravity support. + # This fits for the Helias 5b reactor design point ( F. and Bykov, V. design of Helias 5-B. (nucl Fus. 2013)). + + # Total mass of cooled components + structure_variables.coldmass = ( + tfcoil_variables.m_tf_coils_total + + structure_variables.aintmass + + fwbs_variables.dewmkg + ) + + # Output section + + if output: + po.oheadr(self.outfile, "Support Structure") + po.ovarre( + self.outfile, + "Intercoil support structure mass (from intercoil calculation) (kg)", + "(aintmass)", + structure_variables.aintmass, + ) + po.ovarre( + self.outfile, + "Intercoil support structure mass (scaling, for comparison) (kg)", + "(empiricalmass)", + msupstr, + ) + po.ovarre( + self.outfile, + "Gravity support structure mass (kg)", + "(clgsmass)", + structure_variables.clgsmass, + ) + po.ovarre( + self.outfile, + "Mass of cooled components (kg)", + "(coldmass)", + structure_variables.coldmass, + ) + + def blanket_neutronics(self): + """Routine to calculate neutronic properties for a stellarator""" + + # heating of the blanket + if fwbs_variables.breedmat == 1: + fwbs_variables.breeder = "Orthosilicate" + fwbs_variables.densbreed = 1.50e3 + elif fwbs_variables.breedmat == 2: + fwbs_variables.breeder = "Metatitanate" + fwbs_variables.densbreed = 1.78e3 + else: + fwbs_variables.breeder = ( + "Zirconate" # (In reality, rarely used - activation problems) + ) + fwbs_variables.densbreed = 2.12e3 + + fwbs_variables.m_blkt_total = ( + fwbs_variables.vol_blkt_total * fwbs_variables.densbreed + ) + self.hcpb.nuclear_heating_blanket() + + # Heating of the magnets + self.hcpb.nuclear_heating_magnets(False) + + # Rough estimate of TF coil volume used, assuming 25% of the total + # TF coil perimeter is inboard, 75% outboard + tf_volume = ( + 0.25 * tfcoil_variables.len_tf_coil * tfcoil_variables.a_tf_inboard_total + + 0.75 + * tfcoil_variables.len_tf_coil + * tfcoil_variables.a_tf_leg_outboard + * tfcoil_variables.n_tf_coils + ) + + fwbs_variables.ptfnucpm3 = fwbs_variables.p_tf_nuclear_heat_mw / tf_volume + + # heating of the shield + self.hcpb.nuclear_heating_shield() + + # Energy multiplication factor + fwbs_variables.f_p_blkt_multiplication = 1.269 + + # Use older model to calculate neutron fluence since it + # is not calculated in the CCFE blanket model + ( + _, + _, + _, + fwbs_variables.nflutf, + _, + _, + _, + _, + _, + _, + ) = self.sc_tf_coil_nuclear_heating_iter90() + + # blktlife calculation left entierly to availability + # Cannot find calculation for vvhemax in CCFE blanket + + def st_fwbs(self, output: bool): + """Routine to calculate first wall, blanket and shield properties + for a stellarator + author: P J Knight, CCFE, Culham Science Centre + author: F Warmer, IPP Greifswald + outfile : input integer : Fortran output unit identifier + iprint : input integer : Switch to write output to file (1=yes) + This routine calculates a stellarator's first wall, blanket and + shield properties. + It calculates the nuclear heating in the blanket / shield, and + estimates the volume and masses of the first wall, + blanket, shield and vacuum vessel. +

The arrays coef(i,j) and decay(i,j) + are used for exponential decay approximations of the + (superconducting) TF coil nuclear parameters. +

+ Note: Costing and mass calculations elsewhere assume + stainless steel only. +

The method is the same as for tokamaks (as performed via + fwbs), except for the volume calculations, + which scale the surface area of the components from that + of the plasma. + """ + fwbs_variables.life_fw_fpy = min( + cost_variables.abktflnc / physics_variables.pflux_fw_neutron_mw, + cost_variables.life_plant, + ) + + # First wall inboard, outboard areas (assume 50% of total each) + build_variables.a_fw_inboard = 0.5e0 * build_variables.a_fw_total + build_variables.a_fw_outboard = 0.5e0 * build_variables.a_fw_total + + # Blanket volume; assume that its surface area is scaled directly from the + # plasma surface area. + # Uses fwbs_variables.fhole etc. to take account of gaps due to ports etc. + + r1 = physics_variables.rminor + 0.5e0 * ( + build_variables.dr_fw_plasma_gap_inboard + + build_variables.dr_fw_inboard + + build_variables.dr_fw_plasma_gap_outboard + + build_variables.dr_fw_outboard + ) + if heat_transport_variables.ipowerflow == 0: + build_variables.a_blkt_total_surface = ( + physics_variables.a_plasma_surface + * r1 + / physics_variables.rminor + * (1.0e0 - fwbs_variables.fhole) + ) + else: + build_variables.a_blkt_total_surface = ( + physics_variables.a_plasma_surface + * r1 + / physics_variables.rminor + * ( + 1.0e0 + - fwbs_variables.fhole + - fwbs_variables.f_ster_div_single + - fwbs_variables.f_a_fw_outboard_hcd + ) + ) + + build_variables.a_blkt_inboard_surface = ( + 0.5e0 * build_variables.a_blkt_total_surface + ) + build_variables.a_blkt_outboard_surface = ( + 0.5e0 * build_variables.a_blkt_total_surface + ) + + fwbs_variables.vol_blkt_inboard = ( + build_variables.a_blkt_inboard_surface * build_variables.dr_blkt_inboard + ) + fwbs_variables.vol_blkt_outboard = ( + build_variables.a_blkt_outboard_surface * build_variables.dr_blkt_outboard + ) + fwbs_variables.vol_blkt_total = ( + fwbs_variables.vol_blkt_inboard + fwbs_variables.vol_blkt_outboard + ) + + # Shield volume + # Uses fvolsi, fwbs_variables.fvolso as area coverage factors + + r1 = r1 + 0.5e0 * ( + build_variables.dr_blkt_inboard + build_variables.dr_blkt_outboard + ) + build_variables.a_shld_total_surface = ( + physics_variables.a_plasma_surface * r1 / physics_variables.rminor + ) + build_variables.a_shld_inboard_surface = ( + 0.5e0 * build_variables.a_shld_total_surface * fwbs_variables.fvolsi + ) + build_variables.a_shld_outboard_surface = ( + 0.5e0 * build_variables.a_shld_total_surface * fwbs_variables.fvolso + ) + + vol_shld_inboard = ( + build_variables.a_shld_inboard_surface * build_variables.dr_shld_inboard + ) + vol_shld_outboard = ( + build_variables.a_shld_outboard_surface * build_variables.dr_shld_outboard + ) + fwbs_variables.vol_shld_total = vol_shld_inboard + vol_shld_outboard + + # Neutron power lost through holes in first wall (eventually absorbed by + # shield) + + fwbs_variables.pnucloss = ( + physics_variables.p_neutron_total_mw * fwbs_variables.fhole + ) + + # The peaking factor, obtained as precalculated parameter + fwbs_variables.wallpf = ( + stellarator_configuration.stella_config_neutron_peakfactor + ) + + # Blanket neutronics calculations + if fwbs_variables.blktmodel == 1: + self.blanket_neutronics() + + if heat_transport_variables.ipowerflow == 1: + fwbs_variables.p_div_nuclear_heat_total_mw = ( + physics_variables.p_neutron_total_mw + * fwbs_variables.f_ster_div_single + ) + fwbs_variables.p_fw_hcd_nuclear_heat_mw = ( + physics_variables.p_neutron_total_mw + * fwbs_variables.f_a_fw_outboard_hcd + ) + fwbs_variables.p_fw_nuclear_heat_total_mw = ( + physics_variables.p_neutron_total_mw + - fwbs_variables.p_div_nuclear_heat_total_mw + - fwbs_variables.pnucloss + - fwbs_variables.p_fw_hcd_nuclear_heat_mw + ) + + fwbs_variables.pradloss = ( + physics_variables.p_plasma_rad_mw * fwbs_variables.fhole + ) + fwbs_variables.p_div_rad_total_mw = ( + physics_variables.p_plasma_rad_mw * fwbs_variables.f_ster_div_single + ) + fwbs_variables.p_fw_hcd_rad_total_mw = ( + physics_variables.p_plasma_rad_mw + * fwbs_variables.f_a_fw_outboard_hcd + ) + fwbs_variables.p_fw_rad_total_mw = ( + physics_variables.p_plasma_rad_mw + - fwbs_variables.p_div_rad_total_mw + - fwbs_variables.pradloss + - fwbs_variables.p_fw_hcd_rad_total_mw + ) + + heat_transport_variables.p_fw_coolant_pump_mw = ( + heat_transport_variables.f_p_fw_coolant_pump_total_heat + * ( + fwbs_variables.p_fw_nuclear_heat_total_mw + + fwbs_variables.p_fw_rad_total_mw + + current_drive_variables.p_beam_orbit_loss_mw + ) + ) + heat_transport_variables.p_blkt_coolant_pump_mw = ( + heat_transport_variables.f_p_blkt_coolant_pump_total_heat + * fwbs_variables.p_blkt_nuclear_heat_total_mw + ) + heat_transport_variables.p_shld_coolant_pump_mw = ( + heat_transport_variables.f_p_shld_coolant_pump_total_heat + * fwbs_variables.p_shld_nuclear_heat_mw + ) + heat_transport_variables.p_div_coolant_pump_mw = ( + heat_transport_variables.f_p_div_coolant_pump_total_heat + * ( + physics_variables.p_plasma_separatrix_mw + + fwbs_variables.p_div_nuclear_heat_total_mw + + fwbs_variables.p_div_rad_total_mw + ) + ) + + # Void fraction in first wall / breeding zone, + # for use in fwbs_variables.m_fw_total and coolvol calculation below + + f_a_fw_coolant_inboard = ( + 1.0e0 + - fwbs_variables.fblbe + - fwbs_variables.fblbreed + - fwbs_variables.fblss + ) + f_a_fw_coolant_outboard = f_a_fw_coolant_inboard + + else: + fwbs_variables.pnuc_cp = 0.0e0 + + if heat_transport_variables.ipowerflow == 0: + # Energy-multiplied neutron power + + pneut2 = ( + physics_variables.p_neutron_total_mw + - fwbs_variables.pnucloss + - fwbs_variables.pnuc_cp + ) * fwbs_variables.f_p_blkt_multiplication + + fwbs_variables.p_blkt_multiplication_mw = pneut2 - ( + physics_variables.p_neutron_total_mw + - fwbs_variables.pnucloss + - fwbs_variables.pnuc_cp + ) + + # Nuclear heating in the blanket + + decaybl = 0.075e0 / ( + 1.0e0 + - fwbs_variables.f_a_blkt_cooling_channels + - fwbs_variables.fblli2o + - fwbs_variables.fblbe + ) + + fwbs_variables.p_blkt_nuclear_heat_total_mw = pneut2 * ( + 1.0e0 - np.exp(-build_variables.dr_blkt_outboard / decaybl) + ) + + # Nuclear heating in the shield + fwbs_variables.p_shld_nuclear_heat_mw = ( + pneut2 - fwbs_variables.p_blkt_nuclear_heat_total_mw + ) + + # Superconducting coil shielding calculations + ( + coilhtmx, + dpacop, + htheci, + fwbs_variables.nflutf, + pheci, + pheco, + ptfiwp, + ptfowp, + raddose, + fwbs_variables.p_tf_nuclear_heat_mw, + ) = self.sc_tf_coil_nuclear_heating_iter90() + + else: # heat_transport_variables.ipowerflow == 1 + # Neutron power incident on divertor (MW) + + fwbs_variables.p_div_nuclear_heat_total_mw = ( + physics_variables.p_neutron_total_mw + * fwbs_variables.f_ster_div_single + ) + + # Neutron power incident on HCD apparatus (MW) + + fwbs_variables.p_fw_hcd_nuclear_heat_mw = ( + physics_variables.p_neutron_total_mw + * fwbs_variables.f_a_fw_outboard_hcd + ) + + # Neutron power deposited in first wall, blanket and shield (MW) + + pnucfwbs = ( + physics_variables.p_neutron_total_mw + - fwbs_variables.p_div_nuclear_heat_total_mw + - fwbs_variables.pnucloss + - fwbs_variables.pnuc_cp + - fwbs_variables.p_fw_hcd_nuclear_heat_mw + ) + + # Split between inboard and outboard by first wall area fractions + + pnucfwbsi = ( + pnucfwbs * build_variables.a_fw_inboard / build_variables.a_fw_total + ) + pnucfwbso = ( + pnucfwbs * build_variables.a_fw_outboard / build_variables.a_fw_total + ) + + # Radiation power incident on divertor (MW) + + fwbs_variables.p_fw_hcd_rad_total_mw = ( + physics_variables.p_plasma_rad_mw + * fwbs_variables.f_a_fw_outboard_hcd + ) + + # Radiation power incident on HCD apparatus (MW) + + fwbs_variables.p_fw_hcd_rad_total_mw = ( + physics_variables.p_plasma_rad_mw + * fwbs_variables.f_a_fw_outboard_hcd + ) + + # Radiation power lost through holes (eventually hits shield) (MW) + + fwbs_variables.pradloss = ( + physics_variables.p_plasma_rad_mw * fwbs_variables.fhole + ) + + # Radiation power incident on first wall (MW) + + fwbs_variables.p_fw_rad_total_mw = ( + physics_variables.p_plasma_rad_mw + - fwbs_variables.p_div_rad_total_mw + - fwbs_variables.pradloss + - fwbs_variables.p_fw_hcd_rad_total_mw + ) + + # Calculate the power deposited in the first wall, blanket and shield, + # and the required coolant pumping power + + # If we have chosen pressurised water as the coolant, set the + # coolant outlet temperature as 20 deg C below the boiling point + + if fwbs_variables.i_blkt_coolant_type == 2: + if fwbs_variables.irefprop: + fwbs_variables.temp_blkt_coolant_out = ( + FluidProperties.of( + "Water", + pressure=fwbs_variables.coolp, + vapor_quality=0, + ) + - 20 + ) + else: + fwbs_variables.temp_blkt_coolant_out = ( + 273.15 + + 168.396 + + 0.314653 / fwbs_variables.coolp + + -0.000728 / fwbs_variables.coolp**2 + + 31.588979 * np.log(fwbs_variables.coolp) + + 11.473141 * fwbs_variables.coolp + + -0.575335 * fwbs_variables.coolp**2 + + 0.013165 * fwbs_variables.coolp**3 + ) - 20 + + bfwi = 0.5e0 * build_variables.dr_fw_inboard + bfwo = 0.5e0 * build_variables.dr_fw_outboard + + f_a_fw_coolant_inboard = ( + fwbs_variables.radius_fw_channel + * fwbs_variables.radius_fw_channel + / (bfwi * bfwi) + ) # inboard FW coolant void fraction + f_a_fw_coolant_outboard = ( + fwbs_variables.radius_fw_channel + * fwbs_variables.radius_fw_channel + / (bfwo * bfwo) + ) # outboard FW coolant void fraction + + # First wall decay length (m) - improved calculation required + + decayfwi = fwbs_variables.declfw + decayfwo = fwbs_variables.declfw + + # Surface heat flux on first wall (MW) (sum = fwbs_variables.p_fw_rad_total_mw) + + psurffwi = ( + fwbs_variables.p_fw_rad_total_mw + * build_variables.a_fw_inboard + / build_variables.a_fw_total + ) + psurffwo = ( + fwbs_variables.p_fw_rad_total_mw + * build_variables.a_fw_outboard + / build_variables.a_fw_total + ) + + # Simple blanket model (fwbs_variables.i_p_coolant_pumping = 0 or 1) is assumed for stellarators + + # The power deposited in the first wall, breeder zone and shield is + # calculated according to their dimensions and materials assuming + # an exponential attenuation of nuclear heating with increasing + # radial distance. The pumping power for the coolant is calculated + # as a fraction of the total thermal power deposited in the + # coolant. + + p_fw_inboard_nuclear_heat_mw = pnucfwbsi * ( + 1.0e0 - np.exp(-2.0e0 * bfwi / decayfwi) + ) + p_fw_outboard_nuclear_heat_mw = pnucfwbso * ( + 1.0e0 - np.exp(-2.0e0 * bfwo / decayfwo) + ) + + # Neutron power reaching blanket and shield (MW) + + pnucbsi = pnucfwbsi - p_fw_inboard_nuclear_heat_mw + pnucbso = pnucfwbso - p_fw_outboard_nuclear_heat_mw + + # Blanket decay length (m) - improved calculation required + + decaybzi = fwbs_variables.declblkt + decaybzo = fwbs_variables.declblkt + + # Neutron power deposited in breeder zone (MW) + + pnucbzi = pnucbsi * ( + 1.0e0 - np.exp(-build_variables.dr_blkt_inboard / decaybzi) + ) + pnucbzo = pnucbso * ( + 1.0e0 - np.exp(-build_variables.dr_blkt_outboard / decaybzo) + ) + + # Calculate coolant pumping powers from input fraction. + # The pumping power is assumed to be a fraction, fpump, of the + # incident thermal power to each component so that + # htpmw_i = fpump_i*C, where C is the non-pumping thermal power + # deposited in the coolant + + # First wall and Blanket pumping power (MW) + + if fwbs_variables.i_p_coolant_pumping == 0: + # Use input + pass + elif fwbs_variables.i_p_coolant_pumping == 1: + heat_transport_variables.p_fw_coolant_pump_mw = ( + heat_transport_variables.f_p_fw_coolant_pump_total_heat + * ( + p_fw_inboard_nuclear_heat_mw + + p_fw_outboard_nuclear_heat_mw + + psurffwi + + psurffwo + + current_drive_variables.p_beam_orbit_loss_mw + ) + ) + heat_transport_variables.p_blkt_coolant_pump_mw = ( + heat_transport_variables.f_p_blkt_coolant_pump_total_heat + * ( + pnucbzi * fwbs_variables.f_p_blkt_multiplication + + pnucbzo * fwbs_variables.f_p_blkt_multiplication + ) + ) + else: + raise ProcessValueError( + "i_p_coolant_pumping = 0 or 1 only for stellarator" + ) + + fwbs_variables.p_blkt_multiplication_mw = ( + heat_transport_variables.f_p_blkt_coolant_pump_total_heat + * (pnucbzi * fwbs_variables.f_p_blkt_multiplication + pnucbzo) + * (fwbs_variables.f_p_blkt_multiplication - 1.0e0) + ) + + # Total nuclear heating of first wall (MW) + + fwbs_variables.p_fw_nuclear_heat_total_mw = ( + p_fw_inboard_nuclear_heat_mw + p_fw_outboard_nuclear_heat_mw + ) + + # Total nuclear heating of blanket (MW) + + fwbs_variables.p_blkt_nuclear_heat_total_mw = ( + pnucbzi + pnucbzo + ) * fwbs_variables.f_p_blkt_multiplication + + fwbs_variables.p_blkt_multiplication_mw = ( + fwbs_variables.p_blkt_multiplication_mw + + (pnucbzi + pnucbzo) + * (fwbs_variables.f_p_blkt_multiplication - 1.0e0) + ) + + # Calculation of shield and divertor powers + # Shield and divertor powers and pumping powers are calculated using the same + # simplified method as the first wall and breeder zone when fwbs_variables.i_p_coolant_pumping = 1. + # i.e. the pumping power is a fraction of the total thermal power deposited in the + # coolant. + + # Neutron power reaching the shield (MW) + # The power lost from the fwbs_variables.fhole area fraction is assumed to be incident upon the shield + + pnucsi = ( + pnucbsi + - pnucbzi + + (fwbs_variables.pnucloss + fwbs_variables.pradloss) + * build_variables.a_fw_inboard + / build_variables.a_fw_total + ) + pnucso = ( + pnucbso + - pnucbzo + + (fwbs_variables.pnucloss + fwbs_variables.pradloss) + * build_variables.a_fw_outboard + / build_variables.a_fw_total + ) + + # Improved calculation of shield power decay lengths required + + decayshldi = fwbs_variables.declshld + decayshldo = fwbs_variables.declshld + + # Neutron power deposited in the shield (MW) + + pnucshldi = pnucsi * ( + 1.0e0 - np.exp(-build_variables.dr_shld_inboard / decayshldi) + ) + pnucshldo = pnucso * ( + 1.0e0 - np.exp(-build_variables.dr_shld_outboard / decayshldo) + ) + + fwbs_variables.p_shld_nuclear_heat_mw = pnucshldi + pnucshldo + + # Calculate coolant pumping powers from input fraction. + # The pumping power is assumed to be a fraction, fpump, of the incident + # thermal power to each component so that, + # htpmw_i = fpump_i*C + # where C is the non-pumping thermal power deposited in the coolant + + if fwbs_variables.i_p_coolant_pumping == 1: + # Shield pumping power (MW) + heat_transport_variables.p_shld_coolant_pump_mw = ( + heat_transport_variables.f_p_shld_coolant_pump_total_heat + * (pnucshldi + pnucshldo) + ) + + # Divertor pumping power (MW) + heat_transport_variables.p_div_coolant_pump_mw = ( + heat_transport_variables.f_p_div_coolant_pump_total_heat + * ( + physics_variables.p_plasma_separatrix_mw + + fwbs_variables.p_div_nuclear_heat_total_mw + + fwbs_variables.p_div_rad_total_mw + ) + ) + + # Remaining neutron power to coils and else:where. This is assumed + # (for superconducting coils at least) to be absorbed by the + # coils, and so contributes to the cryogenic load + + if tfcoil_variables.i_tf_sup == 1: + fwbs_variables.p_tf_nuclear_heat_mw = ( + pnucsi + pnucso - pnucshldi - pnucshldo + ) + else: # resistive coils + fwbs_variables.p_tf_nuclear_heat_mw = 0.0e0 + + # Divertor mass + # N.B. divertor_variables.a_div_surface_total is calculated in stdiv after this point, so will + # be zero on first lap, hence the initial approximation + + if self.first_call_stfwbs: + divertor_variables.a_div_surface_total = 50.0e0 + self.first_call_stfwbs = False + + divertor_variables.m_div_plate = ( + divertor_variables.a_div_surface_total + * divertor_variables.den_div_structure + * (1.0e0 - divertor_variables.f_vol_div_coolant) + * divertor_variables.dx_div_plate + ) + + # Start adding components of the coolant mass: + # Divertor coolant volume (m3) + + coolvol = ( + divertor_variables.a_div_surface_total + * divertor_variables.f_vol_div_coolant + * divertor_variables.dx_div_plate + ) + + # Blanket mass, excluding coolant + + if fwbs_variables.blktmodel == 0: + if (fwbs_variables.blkttype == 1) or ( + fwbs_variables.blkttype == 2 + ): # liquid breeder (WCLL or HCLL) + fwbs_variables.wtbllipb = ( + fwbs_variables.vol_blkt_total * fwbs_variables.fbllipb * 9400.0e0 + ) + fwbs_variables.m_blkt_lithium = ( + fwbs_variables.vol_blkt_total * fwbs_variables.fblli * 534.0e0 + ) + fwbs_variables.m_blkt_total = ( + fwbs_variables.wtbllipb + fwbs_variables.m_blkt_lithium + ) + else: # solid breeder (HCPB); always for ipowerflow=0 + fwbs_variables.m_blkt_li2o = ( + fwbs_variables.vol_blkt_total * fwbs_variables.fblli2o * 2010.0e0 + ) + fwbs_variables.m_blkt_beryllium = ( + fwbs_variables.vol_blkt_total * fwbs_variables.fblbe * 1850.0e0 + ) + fwbs_variables.m_blkt_total = ( + fwbs_variables.m_blkt_li2o + fwbs_variables.m_blkt_beryllium + ) + + fwbs_variables.m_blkt_steel_total = ( + fwbs_variables.vol_blkt_total + * fwbs_variables.den_steel + * fwbs_variables.fblss + ) + fwbs_variables.m_blkt_vanadium = ( + fwbs_variables.vol_blkt_total * 5870.0e0 * fwbs_variables.fblvd + ) + + fwbs_variables.m_blkt_total = ( + fwbs_variables.m_blkt_total + + fwbs_variables.m_blkt_steel_total + + fwbs_variables.m_blkt_vanadium + ) + + else: # volume fractions proportional to sub-assembly thicknesses + fwbs_variables.m_blkt_steel_total = fwbs_variables.den_steel * ( + fwbs_variables.vol_blkt_inboard + / build_variables.dr_blkt_inboard + * ( + build_variables.blbuith * fwbs_variables.fblss + + build_variables.blbmith * (1.0e0 - fwbs_variables.fblhebmi) + + build_variables.blbpith * (1.0e0 - fwbs_variables.fblhebpi) + ) + + fwbs_variables.vol_blkt_outboard + / build_variables.dr_blkt_outboard + * ( + build_variables.blbuoth * fwbs_variables.fblss + + build_variables.blbmoth * (1.0e0 - fwbs_variables.fblhebmo) + + build_variables.blbpoth * (1.0e0 - fwbs_variables.fblhebpo) + ) + ) + fwbs_variables.m_blkt_beryllium = ( + 1850.0e0 + * fwbs_variables.fblbe + * ( + ( + fwbs_variables.vol_blkt_inboard + * build_variables.blbuith + / build_variables.dr_blkt_inboard + ) + + ( + fwbs_variables.vol_blkt_outboard + * build_variables.blbuoth + / build_variables.dr_blkt_outboard + ) + ) + ) + fwbs_variables.whtblbreed = ( + fwbs_variables.densbreed + * fwbs_variables.fblbreed + * ( + ( + fwbs_variables.vol_blkt_inboard + * build_variables.blbuith + / build_variables.dr_blkt_inboard + ) + + ( + fwbs_variables.vol_blkt_outboard + * build_variables.blbuoth + / build_variables.dr_blkt_outboard + ) + ) + ) + fwbs_variables.m_blkt_total = ( + fwbs_variables.m_blkt_steel_total + + fwbs_variables.m_blkt_beryllium + + fwbs_variables.whtblbreed + ) + + fwbs_variables.f_a_blkt_cooling_channels = ( + fwbs_variables.vol_blkt_inboard + / fwbs_variables.vol_blkt_total + * ( # inboard portion + (build_variables.blbuith / build_variables.dr_blkt_inboard) + * ( + 1.0e0 + - fwbs_variables.fblbe + - fwbs_variables.fblbreed + - fwbs_variables.fblss + ) + + (build_variables.blbmith / build_variables.dr_blkt_inboard) + * fwbs_variables.fblhebmi + + (build_variables.blbpith / build_variables.dr_blkt_inboard) + * fwbs_variables.fblhebpi + ) + ) + fwbs_variables.f_a_blkt_cooling_channels = ( + fwbs_variables.f_a_blkt_cooling_channels + + fwbs_variables.vol_blkt_outboard + / fwbs_variables.vol_blkt_total + * ( # outboard portion + (build_variables.blbuoth / build_variables.dr_blkt_outboard) + * ( + 1.0e0 + - fwbs_variables.fblbe + - fwbs_variables.fblbreed + - fwbs_variables.fblss + ) + + (build_variables.blbmoth / build_variables.dr_blkt_outboard) + * fwbs_variables.fblhebmo + + (build_variables.blbpoth / build_variables.dr_blkt_outboard) + * fwbs_variables.fblhebpo + ) + ) + + # When fwbs_variables.blktmodel > 0, although the blanket is by definition helium-cooled + # in this case, the shield etc. are assumed to be water-cooled, and since + # water is heavier the calculation for fwbs_variables.m_fw_blkt_div_coolant_total is better done with + # i_blkt_coolant_type=2 if fwbs_variables.blktmodel > 0; thus we can ignore the helium coolant mass + # in the blanket. + + if fwbs_variables.blktmodel == 0: + coolvol = ( + coolvol + + fwbs_variables.vol_blkt_total + * fwbs_variables.f_a_blkt_cooling_channels + ) + + # Shield mass + fwbs_variables.whtshld = ( + fwbs_variables.vol_shld_total + * fwbs_variables.den_steel + * (1.0e0 - fwbs_variables.vfshld) + ) + + coolvol = coolvol + fwbs_variables.vol_shld_total * fwbs_variables.vfshld + + # Penetration shield (set = internal shield) + + fwbs_variables.wpenshld = fwbs_variables.whtshld + + if heat_transport_variables.ipowerflow == 0: + # First wall mass + # (first wall area is calculated else:where) + + fwbs_variables.m_fw_total = ( + build_variables.a_fw_total + * (build_variables.dr_fw_inboard + build_variables.dr_fw_outboard) + / 2.0e0 + * fwbs_variables.den_steel + * (1.0e0 - fwbs_variables.fwclfr) + ) + + # Surface areas adjacent to plasma + + coolvol = ( + coolvol + + build_variables.a_fw_total + * (build_variables.dr_fw_inboard + build_variables.dr_fw_outboard) + / 2.0e0 + * fwbs_variables.fwclfr + ) + + else: + fwbs_variables.m_fw_total = fwbs_variables.den_steel * ( + build_variables.a_fw_inboard + * build_variables.dr_fw_inboard + * (1.0e0 - f_a_fw_coolant_inboard) + + build_variables.a_fw_outboard + * build_variables.dr_fw_outboard + * (1.0e0 - f_a_fw_coolant_outboard) + ) + coolvol = ( + coolvol + + build_variables.a_fw_inboard + * build_variables.dr_fw_inboard + * f_a_fw_coolant_inboard + + build_variables.a_fw_outboard + * build_variables.dr_fw_outboard + * f_a_fw_coolant_outboard + ) + + # Average first wall coolant fraction, only used by old routines + # in fispact.f90, safety.f90 + + fwbs_variables.fwclfr = ( + build_variables.a_fw_inboard + * build_variables.dr_fw_inboard + * f_a_fw_coolant_inboard + + build_variables.a_fw_outboard + * build_variables.dr_fw_outboard + * f_a_fw_coolant_outboard + ) / ( + build_variables.a_fw_total + * 0.5e0 + * (build_variables.dr_fw_inboard + build_variables.dr_fw_outboard) + ) + + # Mass of coolant = volume * density at typical coolant + # temperatures and pressures + # N.B. for fwbs_variables.blktmodel > 0, mass of *water* coolant in the non-blanket + # structures is used (see comment above) + + if (fwbs_variables.blktmodel > 0) or ( + fwbs_variables.i_blkt_coolant_type == 2 + ): # pressurised water coolant + fwbs_variables.m_fw_blkt_div_coolant_total = coolvol * 806.719e0 + else: # gaseous helium coolant + fwbs_variables.m_fw_blkt_div_coolant_total = coolvol * 1.517e0 + + # Assume external cryostat is a torus with circular cross-section, + # centred on plasma major radius. + # N.B. No check made to see if coils etc. lie wholly within cryostat... + + # External cryostat outboard major radius (m) + + fwbs_variables.r_cryostat_inboard = ( + build_variables.r_tf_outboard_mid + + 0.5e0 * build_variables.dr_tf_outboard + + fwbs_variables.dr_pf_cryostat + ) + adewex = fwbs_variables.r_cryostat_inboard - physics_variables.rmajor + + # External cryostat volume + + fwbs_variables.vol_cryostat = ( + 4.0e0 + * (np.pi**2) + * physics_variables.rmajor + * adewex + * build_variables.dr_cryostat + ) + + # Internal vacuum vessel volume + # fwbs_variables.fvoldw accounts for ports, support, etc. additions + + r1 = physics_variables.rminor + 0.5e0 * ( + build_variables.dr_fw_plasma_gap_inboard + + build_variables.dr_fw_inboard + + build_variables.dr_blkt_inboard + + build_variables.dr_shld_inboard + + build_variables.dr_fw_plasma_gap_outboard + + build_variables.dr_fw_outboard + + build_variables.dr_blkt_outboard + + build_variables.dr_shld_outboard + ) + fwbs_variables.vol_vv = ( + (build_variables.dr_vv_inboard + build_variables.dr_vv_outboard) + / 2.0e0 + * physics_variables.a_plasma_surface + * r1 + / physics_variables.rminor + * fwbs_variables.fvoldw + ) + + # Vacuum vessel mass + + fwbs_variables.m_vv = fwbs_variables.vol_vv * fwbs_variables.den_steel + + # Sum of internal vacuum vessel and external cryostat masses + + fwbs_variables.dewmkg = ( + fwbs_variables.vol_vv + fwbs_variables.vol_cryostat + ) * fwbs_variables.den_steel + + if output: + # Output section + + po.oheadr(self.outfile, "First Wall / Blanket / Shield") + po.ovarre( + self.outfile, + "Average neutron wall load (MW/m2)", + "(pflux_fw_neutron_mw)", + physics_variables.pflux_fw_neutron_mw, + ) + if fwbs_variables.blktmodel > 0: + po.ovarre( + self.outfile, + "Neutron wall load peaking factor", + "(wallpf)", + fwbs_variables.wallpf, + ) + + po.ovarre( + self.outfile, + "First wall full-power lifetime (years)", + "(life_fw_fpy)", + fwbs_variables.life_fw_fpy, + ) + + po.ovarre( + self.outfile, + "Inboard shield thickness (m)", + "(dr_shld_inboard)", + build_variables.dr_shld_inboard, + ) + po.ovarre( + self.outfile, + "Outboard shield thickness (m)", + "(dr_shld_outboard)", + build_variables.dr_shld_outboard, + ) + po.ovarre( + self.outfile, + "Top shield thickness (m)", + "(dz_shld_upper)", + build_variables.dz_shld_upper, + ) + + if fwbs_variables.blktmodel > 0: + po.ovarre( + self.outfile, + "Inboard breeding zone thickness (m)", + "(blbuith)", + build_variables.blbuith, + ) + po.ovarre( + self.outfile, + "Inboard box manifold thickness (m)", + "(blbmith)", + build_variables.blbmith, + ) + po.ovarre( + self.outfile, + "Inboard back plate thickness (m)", + "(blbpith)", + build_variables.blbpith, + ) + + po.ovarre( + self.outfile, + "Inboard blanket thickness (m)", + "(dr_blkt_inboard)", + build_variables.dr_blkt_inboard, + ) + if fwbs_variables.blktmodel > 0: + po.ovarre( + self.outfile, + "Outboard breeding zone thickness (m)", + "(blbuoth)", + build_variables.blbuoth, + ) + po.ovarre( + self.outfile, + "Outboard box manifold thickness (m)", + "(blbmoth)", + build_variables.blbmoth, + ) + po.ovarre( + self.outfile, + "Outboard back plate thickness (m)", + "(blbpoth)", + build_variables.blbpoth, + ) + + po.ovarre( + self.outfile, + "Outboard blanket thickness (m)", + "(dr_blkt_outboard)", + build_variables.dr_blkt_outboard, + ) + po.ovarre( + self.outfile, + "Top blanket thickness (m)", + "(dz_blkt_upper)", + build_variables.dz_blkt_upper, + ) + + if (heat_transport_variables.ipowerflow == 0) and ( + fwbs_variables.blktmodel == 0 + ): + po.osubhd(self.outfile, "Coil nuclear parameters :") + po.ovarre( + self.outfile, "Peak magnet heating (MW/m3)", "(coilhtmx)", coilhtmx + ) + po.ovarre( + self.outfile, + "Inboard coil winding pack heating (MW)", + "(ptfiwp)", + ptfiwp, + ) + po.ovarre( + self.outfile, + "Outboard coil winding pack heating (MW)", + "(ptfowp)", + ptfowp, + ) + po.ovarre( + self.outfile, "Peak coil case heating (MW/m3)", "(htheci)", htheci + ) + po.ovarre( + self.outfile, "Inboard coil case heating (MW)", "(pheci)", pheci + ) + po.ovarre( + self.outfile, "Outboard coil case heating (MW)", "(pheco)", pheco + ) + po.ovarre(self.outfile, "Insulator dose (rad)", "(raddose)", raddose) + po.ovarre( + self.outfile, + "Maximum neutron fluence (n/m2)", + "(nflutf)", + fwbs_variables.nflutf, + ) + po.ovarre( + self.outfile, + "Copper stabiliser displacements/atom", + "(dpacop)", + dpacop, + ) + + if fwbs_variables.blktmodel == 0: + po.osubhd(self.outfile, "Nuclear heating :") + po.ovarre( + self.outfile, + "Blanket heating (including energy multiplication) (MW)", + "(p_blkt_nuclear_heat_total_mw)", + fwbs_variables.p_blkt_nuclear_heat_total_mw, + ) + po.ovarre( + self.outfile, + "Shield nuclear heating (MW)", + "(p_shld_nuclear_heat_mw)", + fwbs_variables.p_shld_nuclear_heat_mw, + ) + po.ovarre( + self.outfile, + "Coil nuclear heating (MW)", + "(p_tf_nuclear_heat_mw)", + fwbs_variables.p_tf_nuclear_heat_mw, + ) + else: + po.osubhd(self.outfile, "Blanket neutronics :") + po.ovarre( + self.outfile, + "Blanket heating (including energy multiplication) (MW)", + "(p_blkt_nuclear_heat_total_mw)", + fwbs_variables.p_blkt_nuclear_heat_total_mw, + ) + po.ovarre( + self.outfile, + "Shield heating (MW)", + "(p_shld_nuclear_heat_mw)", + fwbs_variables.p_shld_nuclear_heat_mw, + ) + po.ovarre( + self.outfile, + "Energy multiplication in blanket", + "(f_p_blkt_multiplication)", + fwbs_variables.f_p_blkt_multiplication, + ) + po.ovarin( + self.outfile, + "Number of divertor ports assumed", + "(npdiv)", + fwbs_variables.npdiv, + ) + po.ovarin( + self.outfile, + "Number of inboard H/CD ports assumed", + "(nphcdin)", + fwbs_variables.nphcdin, + ) + po.ovarin( + self.outfile, + "Number of outboard H/CD ports assumed", + "(nphcdout)", + fwbs_variables.nphcdout, + ) + if fwbs_variables.hcdportsize == 1: + po.ocmmnt( + self.outfile, " (small heating/current drive ports assumed)" + ) + else: + po.ocmmnt( + self.outfile, " (large heating/current drive ports assumed)" + ) + + if fwbs_variables.breedmat == 1: + po.ocmmnt( + self.outfile, + "Breeder material: Lithium orthosilicate (Li4Si04)", + ) + elif fwbs_variables.breedmat == 2: + po.ocmmnt( + self.outfile, + "Breeder material: Lithium methatitanate (Li2TiO3)", + ) + elif fwbs_variables.breedmat == 3: + po.ocmmnt( + self.outfile, "Breeder material: Lithium zirconate (Li2ZrO3)" + ) + else: # shouldn't get here... + po.ocmmnt(self.outfile, "Unknown breeder material...") + + po.ovarre( + self.outfile, + "Lithium-6 enrichment (%)", + "(f_blkt_li6_enrichment)", + fwbs_variables.f_blkt_li6_enrichment, + ) + po.ovarre( + self.outfile, + "Tritium production rate (g/day)", + "(tritprate)", + fwbs_variables.tritprate, + ) + po.ovarre( + self.outfile, + "Nuclear heating on i/b coil (MW/m3)", + "(pnuctfi)", + fwbs_variables.pnuctfi, + ) + po.ovarre( + self.outfile, + "Nuclear heating on o/b coil (MW/m3)", + "(pnuctfo)", + fwbs_variables.pnuctfo, + ) + po.ovarre( + self.outfile, + "Total nuclear heating on coil (MW)", + "(p_tf_nuclear_heat_mw)", + fwbs_variables.p_tf_nuclear_heat_mw, + ) + po.ovarre( + self.outfile, + "Fast neut. fluence on i/b coil (n/m2)", + "(nflutfi)", + fwbs_variables.nflutfi * 1.0e4, + ) + po.ovarre( + self.outfile, + "Fast neut. fluence on o/b coil (n/m2)", + "(nflutfo)", + fwbs_variables.nflutfo * 1.0e4, + ) + po.ovarre( + self.outfile, + "Minimum final He conc. in IB VV (appm)", + "(vvhemini)", + fwbs_variables.vvhemini, + ) + po.ovarre( + self.outfile, + "Minimum final He conc. in OB VV (appm)", + "(vvhemino)", + fwbs_variables.vvhemino, + ) + po.ovarre( + self.outfile, + "Maximum final He conc. in IB VV (appm)", + "(vvhemaxi)", + fwbs_variables.vvhemaxi, + ) + po.ovarre( + self.outfile, + "Maximum final He conc. in OB VV (appm)", + "(vvhemaxo)", + fwbs_variables.vvhemaxo, + ) + po.ovarre( + self.outfile, + "Blanket lifetime (full power years)", + "(life_blkt_fpy)", + fwbs_variables.life_blkt_fpy, + ) + po.ovarre( + self.outfile, + "Blanket lifetime (calendar years)", + "(t_bl_y)", + fwbs_variables.t_bl_y, + ) + + if (heat_transport_variables.ipowerflow == 1) and ( + fwbs_variables.blktmodel == 0 + ): + po.oblnkl(self.outfile) + po.ovarin( + self.outfile, + "First wall / blanket thermodynamic model", + "(i_thermal_electric_conversion)", + fwbs_variables.i_thermal_electric_conversion, + ) + if fwbs_variables.i_thermal_electric_conversion == 0: + po.ocmmnt(self.outfile, " (Simple calculation)") + + po.osubhd(self.outfile, "Blanket / shield volumes and weights :") + + po.osubhd(self.outfile, "Other volumes, masses and areas :") + po.ovarre( + self.outfile, + "First wall area (m2)", + "(a_fw_total)", + build_variables.a_fw_total, + ) + po.ovarre( + self.outfile, + "First wall mass (kg)", + "(m_fw_total)", + fwbs_variables.m_fw_total, + ) + po.ovarre( + self.outfile, + "External cryostat inner radius (m)", + "", + fwbs_variables.r_cryostat_inboard - 2.0e0 * adewex, + ) + po.ovarre( + self.outfile, + "External cryostat outer radius (m)", + "(r_cryostat_inboard)", + fwbs_variables.r_cryostat_inboard, + ) + po.ovarre( + self.outfile, "External cryostat minor radius (m)", "(adewex)", adewex + ) + po.ovarre( + self.outfile, + "External cryostat shell volume (m^3)", + "(vol_cryostat)", + fwbs_variables.vol_cryostat, + ) + po.ovarre( + self.outfile, + "Internal volume of the cryostat structure (m^3)", + "(vol_cryostat_internal)", + fwbs_variables.vol_cryostat_internal, + ) + po.ovarre( + self.outfile, + "External cryostat mass (kg)", + "", + fwbs_variables.dewmkg - fwbs_variables.m_vv, + ) + po.ovarre( + self.outfile, + "Internal vacuum vessel shell volume (m3)", + "(vol_vv)", + fwbs_variables.vol_vv, + ) + po.ovarre( + self.outfile, + "Vacuum vessel mass (kg)", + "(m_vv)", + fwbs_variables.m_vv, + ) + po.ovarre( + self.outfile, + "Total cryostat + vacuum vessel mass (kg)", + "(dewmkg)", + fwbs_variables.dewmkg, + ) + po.ovarre( + self.outfile, + "Divertor area (m2)", + "(a_div_surface_total)", + divertor_variables.a_div_surface_total, + ) + po.ovarre( + self.outfile, + "Divertor mass (kg)", + "(m_div_plate)", + divertor_variables.m_div_plate, + ) + + def sc_tf_coil_nuclear_heating_iter90(self): + """Superconducting TF coil nuclear heating estimate + author: P J Knight, CCFE, Culham Science Centre + coilhtmx : output real : peak magnet heating (MW/m3) + dpacop : output real : copper stabiliser displacements/atom + htheci : output real : peak TF coil case heating (MW/m3) + nflutf : output real : maximum neutron fluence (n/m2) + pheci : output real : inboard coil case heating (MW) + pheco : output real : outboard coil case heating (MW) + ptfiwp : output real : inboard TF coil winding pack heating (MW) + ptfowp : output real : outboard TF coil winding pack heating (MW) + raddose : output real : insulator dose (rad) + p_tf_nuclear_heat_mw : output real : TF coil nuclear heating (MW) + This subroutine calculates the nuclear heating in the + superconducting TF coils, assuming an exponential neutron + attenuation through the blanket and shield materials. + The estimates are based on 1990 ITER data. +

The arrays coef(i,j) and decay(i,j) + are used for exponential decay approximations of the + (superconducting) TF coil nuclear parameters. +

+ Note: Costing and mass calculations elsewhere assume + stainless steel only. + """ + + ishmat = 0 # stainless steel coil casing is assumed + + if tfcoil_variables.i_tf_sup != 1: # Resistive coils + coilhtmx = 0.0 + ptfiwp = 0.0 + ptfowp = 0.0 + htheci = 0.0 + pheci = 0.0 + pheco = 0.0 + raddose = 0.0 + nflutf = 0.0 + dpacop = 0.0 + p_tf_nuclear_heat_mw = 0.0 + + else: + # TF coil nuclear heating coefficients in region i (first element), + # assuming shield material j (second element where present) + + fact = np.array([8.0, 8.0, 6.0, 4.0, 4.0]) + coef = np.array([ + [10.3, 11.6, 7.08e5, 2.19e18, 3.33e-7], + [8.32, 10.6, 7.16e5, 2.39e18, 3.84e-7], + ]).T + + decay = np.array([ + [10.05, 17.61, 13.82, 13.24, 14.31, 13.26, 13.25], + [10.02, 3.33, 15.45, 14.47, 15.87, 15.25, 17.25], + ]).T + + # N.B. The vacuum vessel appears to be ignored + + dshieq = ( + build_variables.dr_shld_inboard + + build_variables.dr_fw_inboard + + build_variables.dr_blkt_inboard + ) + dshoeq = ( + build_variables.dr_shld_outboard + + build_variables.dr_fw_outboard + + build_variables.dr_blkt_outboard + ) + + # Winding pack radial thickness, including groundwall insulation + + wpthk = ( + tfcoil_variables.dr_tf_wp_with_insulation + + 2.0 * tfcoil_variables.dx_tf_wp_insulation + ) + + # Nuclear heating rate in inboard TF coil (MW/m**3) + + coilhtmx = ( + fact[0] + * physics_variables.pflux_fw_neutron_mw + * coef[0, ishmat] + * np.exp( + -decay[5, ishmat] * (dshieq + tfcoil_variables.dr_tf_plasma_case) + ) + ) + + # Total nuclear heating (MW) + + ptfiwp = ( + coilhtmx + * tfcoil_variables.tfsai + * (1.0 - np.exp(-decay[0, ishmat] * wpthk)) + / decay[0, ishmat] + ) + ptfowp = ( + fact[0] + * physics_variables.pflux_fw_neutron_mw + * coef[0, ishmat] + * np.exp( + -decay[5, ishmat] * (dshoeq + tfcoil_variables.dr_tf_plasma_case) + ) + * tfcoil_variables.tfsao + * (1.0 - np.exp(-decay[0, ishmat] * wpthk)) + / decay[0, ishmat] + ) + + # Nuclear heating in plasma-side TF coil case (MW) + + htheci = ( + fact[1] + * physics_variables.pflux_fw_neutron_mw + * coef[1, ishmat] + * np.exp(-decay[6, ishmat] * dshieq) + ) + pheci = ( + htheci + * tfcoil_variables.tfsai + * (1.0 - np.exp(-decay[1, ishmat] * tfcoil_variables.dr_tf_plasma_case)) + / decay[1, ishmat] + ) + pheco = ( + fact[1] + * physics_variables.pflux_fw_neutron_mw + * coef[1, ishmat] + * np.exp(-decay[6, ishmat] * dshoeq) + * tfcoil_variables.tfsao + * (1.0 - np.exp(-decay[1, ishmat] * tfcoil_variables.dr_tf_plasma_case)) + / decay[1, ishmat] + ) + ptfi = ptfiwp + pheci + ptfo = ptfowp + pheco + + p_tf_nuclear_heat_mw = ptfi + ptfo + + # Full power DT operation years for replacement of TF Coil + # (or plant life) + + fpydt = cost_variables.f_t_plant_available * cost_variables.life_plant + fpsdt = fpydt * 3.154e7 # seconds + + # Insulator dose (rad) + + raddose = ( + coef[2, ishmat] + * fpsdt + * fact[2] + * physics_variables.pflux_fw_neutron_mw + * np.exp( + -decay[2, ishmat] * (dshieq + tfcoil_variables.dr_tf_plasma_case) + ) + ) + + # Maximum neutron fluence in superconductor (n/m**2) + + nflutf = ( + fpsdt + * fact[3] + * physics_variables.pflux_fw_neutron_mw + * coef[3, ishmat] + * np.exp( + -decay[3, ishmat] * (dshieq + tfcoil_variables.dr_tf_plasma_case) + ) + ) + + # Atomic displacement in copper stabilizer + + dpacop = ( + fpsdt + * fact[4] + * physics_variables.pflux_fw_neutron_mw + * coef[4, ishmat] + * np.exp( + -decay[4, ishmat] * (dshieq + tfcoil_variables.dr_tf_plasma_case) + ) + ) + + return ( + coilhtmx, + dpacop, + htheci, + nflutf, + pheci, + pheco, + ptfiwp, + ptfowp, + raddose, + p_tf_nuclear_heat_mw, + ) + + def st_phys(self, output): + """Routine to calculate stellarator plasma physics information + author: P J Knight, CCFE, Culham Science Centre + author: F Warmer, IPP Greifswald + None + This routine calculates the physics quantities relevant to + a stellarator device. + AEA FUS 172: Physics Assessment for the European Reactor Study + """ + # ############################################### + # Calculate plasma composition + # Issue #261 Remove old radiation model + + self.physics.plasma_composition() + + # Calculate density and temperature profile quantities + self.plasma_profile.run() + + # Total field + physics_variables.b_plasma_total = np.sqrt( + physics_variables.b_plasma_toroidal_on_axis**2 + + physics_variables.b_plasma_poloidal_average**2 + ) + + # Check if physics_variables.beta (iteration variable 5) is an iteration variable + if 5 in numerics.ixc: + raise ProcessValueError( + "Beta should not be in ixc if istell>0. Use Constraints 24 and 84 instead" + ) + + # Set physics_variables.beta as a consequence: + # This replaces constraint equation 1 as it is just an equality. + physics_variables.beta_total_vol_avg = ( + physics_variables.beta_fast_alpha + + physics_variables.beta_beam + + 2.0e3 + * constants.RMU0 + * constants.ELECTRON_CHARGE + * ( + physics_variables.nd_plasma_electrons_vol_avg + * physics_variables.temp_plasma_electron_density_weighted_kev + + physics_variables.nd_plasma_ions_total_vol_avg + * physics_variables.temp_plasma_ion_density_weighted_kev + ) + / physics_variables.b_plasma_total**2 + ) + physics_variables.e_plasma_beta = ( + 1.5e0 + * physics_variables.beta_total_vol_avg + * physics_variables.b_plasma_total + * physics_variables.b_plasma_total + / (2.0e0 * constants.RMU0) + * physics_variables.vol_plasma + ) + + physics_variables.rho_star = np.sqrt( + 2.0e0 + * constants.PROTON_MASS + * physics_variables.m_ions_total_amu + * physics_variables.e_plasma_beta + / ( + 3.0e0 + * physics_variables.vol_plasma + * physics_variables.nd_plasma_electron_line + ) + ) / ( + constants.ELECTRON_CHARGE + * physics_variables.b_plasma_toroidal_on_axis + * physics_variables.eps + * physics_variables.rmajor + ) + + # Calculate poloidal field using rotation transform + physics_variables.b_plasma_poloidal_average = ( + physics_variables.rminor + * physics_variables.b_plasma_toroidal_on_axis + / physics_variables.rmajor + * stellarator_variables.iotabar + ) + + # Perform auxiliary power calculations + + st_heat(self, False) + + # Calculate fusion power + + fusion_reactions = reactions.FusionReactionRate(self.plasma_profile) + fusion_reactions.deuterium_branching( + physics_variables.temp_plasma_ion_vol_avg_kev + ) + fusion_reactions.calculate_fusion_rates() + fusion_reactions.set_physics_variables() + + # D-T power density is named differently to differentiate it from the beam given component + physics_variables.p_plasma_dt_mw = ( + physics_variables.dt_power_density_plasma * physics_variables.vol_plasma + ) + physics_variables.p_dhe3_total_mw = ( + physics_variables.dhe3_power_density * physics_variables.vol_plasma + ) + physics_variables.p_dd_total_mw = ( + physics_variables.dd_power_density * physics_variables.vol_plasma + ) + + # Calculate neutral beam slowing down effects + # If ignited, then ignore beam fusion effects + + if (current_drive_variables.p_hcd_beam_injected_total_mw != 0.0e0) and ( + physics_variables.i_plasma_ignited == 0 + ): + ( + physics_variables.beta_beam, + physics_variables.nd_beam_ions_out, + physics_variables.p_beam_alpha_mw, + ) = reactions.beam_fusion( + physics_variables.beamfus0, + physics_variables.betbm0, + physics_variables.b_plasma_poloidal_average, + physics_variables.b_plasma_toroidal_on_axis, + current_drive_variables.c_beam_total, + physics_variables.nd_plasma_electrons_vol_avg, + physics_variables.nd_plasma_fuel_ions_vol_avg, + physics_variables.dlamie, + current_drive_variables.e_beam_kev, + physics_variables.f_plasma_fuel_deuterium, + physics_variables.f_plasma_fuel_tritium, + current_drive_variables.f_beam_tritium, + physics_variables.sigmav_dt_average, + physics_variables.temp_plasma_electron_density_weighted_kev, + physics_variables.temp_plasma_ion_density_weighted_kev, + physics_variables.vol_plasma, + physics_variables.n_charge_plasma_effective_mass_weighted_vol_avg, + ) + physics_variables.fusden_total = ( + physics_variables.fusden_plasma + + 1.0e6 + * physics_variables.p_beam_alpha_mw + / (constants.DT_ALPHA_ENERGY) + / physics_variables.vol_plasma + ) + physics_variables.fusden_alpha_total = ( + physics_variables.fusden_plasma_alpha + + 1.0e6 + * physics_variables.p_beam_alpha_mw + / (constants.DT_ALPHA_ENERGY) + / physics_variables.vol_plasma + ) + physics_variables.p_dt_total_mw = ( + physics_variables.p_plasma_dt_mw + + 5.0e0 * physics_variables.p_beam_alpha_mw + ) + else: + # If no beams present then the total alpha rates and power are the same as the plasma values + physics_variables.fusden_total = physics_variables.fusden_plasma + physics_variables.fusden_alpha_total = physics_variables.fusden_plasma_alpha + physics_variables.p_dt_total_mw = physics_variables.p_plasma_dt_mw + + # Create some derived values and add beam contribution to fusion power + ( + physics_variables.pden_neutron_total_mw, + physics_variables.p_plasma_alpha_mw, + physics_variables.p_alpha_total_mw, + physics_variables.p_plasma_neutron_mw, + physics_variables.p_neutron_total_mw, + physics_variables.p_non_alpha_charged_mw, + physics_variables.pden_alpha_total_mw, + physics_variables.f_pden_alpha_electron_mw, + physics_variables.f_pden_alpha_ions_mw, + physics_variables.p_charged_particle_mw, + physics_variables.p_fusion_total_mw, + ) = reactions.set_fusion_powers( + physics_variables.f_alpha_electron, + physics_variables.f_alpha_ion, + physics_variables.p_beam_alpha_mw, + physics_variables.pden_non_alpha_charged_mw, + physics_variables.pden_plasma_neutron_mw, + physics_variables.vol_plasma, + physics_variables.pden_plasma_alpha_mw, + ) + + physics_variables.beta_fast_alpha = physics_funcs.fast_alpha_beta( + physics_variables.b_plasma_poloidal_average, + physics_variables.b_plasma_toroidal_on_axis, + physics_variables.nd_plasma_electrons_vol_avg, + physics_variables.nd_plasma_fuel_ions_vol_avg, + physics_variables.nd_plasma_ions_total_vol_avg, + physics_variables.temp_plasma_electron_density_weighted_kev, + physics_variables.temp_plasma_ion_density_weighted_kev, + physics_variables.pden_alpha_total_mw, + physics_variables.pden_plasma_alpha_mw, + physics_variables.i_beta_fast_alpha, + ) + + # Neutron wall load + + if physics_variables.i_pflux_fw_neutron == 1: + physics_variables.pflux_fw_neutron_mw = ( + physics_variables.ffwal + * physics_variables.p_neutron_total_mw + / physics_variables.a_plasma_surface + ) + else: + if heat_transport_variables.ipowerflow == 0: + physics_variables.pflux_fw_neutron_mw = ( + (1.0e0 - fwbs_variables.fhole) + * physics_variables.p_neutron_total_mw + / build_variables.a_fw_total + ) + else: + physics_variables.pflux_fw_neutron_mw = ( + ( + 1.0e0 + - fwbs_variables.fhole + - fwbs_variables.f_a_fw_outboard_hcd + - fwbs_variables.f_ster_div_single + ) + * physics_variables.p_neutron_total_mw + / build_variables.a_fw_total + ) + + # Calculate ion/electron equilibration power + + physics_variables.pden_ion_electron_equilibration_mw = rether( + physics_variables.alphan, + physics_variables.alphat, + physics_variables.nd_plasma_electrons_vol_avg, + physics_variables.dlamie, + physics_variables.temp_plasma_electron_vol_avg_kev, + physics_variables.temp_plasma_ion_vol_avg_kev, + physics_variables.n_charge_plasma_effective_mass_weighted_vol_avg, + ) + + # Calculate radiation power + radpwr_data = physics_funcs.calculate_radiation_powers( + self.plasma_profile, + physics_variables.nd_plasma_electron_on_axis, + physics_variables.rminor, + physics_variables.b_plasma_toroidal_on_axis, + physics_variables.aspect, + physics_variables.alphan, + physics_variables.alphat, + physics_variables.tbeta, + physics_variables.temp_plasma_electron_on_axis_kev, + physics_variables.f_sync_reflect, + physics_variables.rmajor, + physics_variables.kappa, + physics_variables.vol_plasma, + ) + physics_variables.pden_plasma_sync_mw = radpwr_data.pden_plasma_sync_mw + physics_variables.pden_plasma_core_rad_mw = radpwr_data.pden_plasma_core_rad_mw + physics_variables.pden_plasma_outer_rad_mw = radpwr_data.pden_plasma_outer_rad_mw + physics_variables.pden_plasma_rad_mw = radpwr_data.pden_plasma_rad_mw + + physics_variables.pden_plasma_core_rad_mw = max( + physics_variables.pden_plasma_core_rad_mw, 0.0e0 + ) + physics_variables.pden_plasma_outer_rad_mw = max( + physics_variables.pden_plasma_outer_rad_mw, 0.0e0 + ) + + physics_variables.p_plasma_inner_rad_mw = ( + physics_variables.pden_plasma_core_rad_mw * physics_variables.vol_plasma + ) # Should probably be vol_core + physics_variables.p_plasma_outer_rad_mw = ( + physics_variables.pden_plasma_outer_rad_mw * physics_variables.vol_plasma + ) + + physics_variables.p_plasma_rad_mw = ( + physics_variables.pden_plasma_rad_mw * physics_variables.vol_plasma + ) + + # Heating power to plasma (= Psol in divertor model) + # Ohmic power is zero in a stellarator + # physics_variables.p_plasma_rad_mw here is core + edge (no SOL) + + powht = ( + physics_variables.f_p_alpha_plasma_deposited + * physics_variables.p_alpha_total_mw + + physics_variables.p_non_alpha_charged_mw + + physics_variables.p_plasma_ohmic_mw + - physics_variables.pden_plasma_rad_mw * physics_variables.vol_plasma + ) + powht = max( + 0.00001e0, powht + ) # To avoid negative heating power. This line is VERY important + + if physics_variables.i_plasma_ignited == 0: + powht = ( + powht + current_drive_variables.p_hcd_injected_total_mw + ) # if not ignited add the auxiliary power + + # Here the implementation sometimes leaves the accessible regime when p_plasma_rad_mw> powht which is unphysical and + # is not taken care of by the rad module. We restrict the radiation power here by the heating power: + physics_variables.p_plasma_rad_mw = max(0.0e0, physics_variables.p_plasma_rad_mw) + + # Power to divertor, = (1-stellarator_variables.f_rad)*Psol + + # The SOL radiation needs to be smaller than the physics_variables.p_plasma_rad_mw + physics_variables.psolradmw = stellarator_variables.f_rad * powht + physics_variables.p_plasma_separatrix_mw = powht - physics_variables.psolradmw + + # Add SOL Radiation to total + physics_variables.p_plasma_rad_mw = ( + physics_variables.p_plasma_rad_mw + physics_variables.psolradmw + ) + + # The following line is unphysical, but prevents -ve sqrt argument + # Should be obsolete if constraint eqn 17 is turned on (but beware - + # this may not be quite correct for stellarators) + physics_variables.p_plasma_separatrix_mw = max( + 0.001e0, physics_variables.p_plasma_separatrix_mw + ) + + # Power transported to the first wall by escaped alpha particles + + physics_variables.p_fw_alpha_mw = physics_variables.p_alpha_total_mw * ( + 1.0e0 - physics_variables.f_p_alpha_plasma_deposited + ) + + # Nominal mean photon wall load + if physics_variables.i_pflux_fw_neutron == 1: + physics_variables.pflux_fw_rad_mw = ( + physics_variables.ffwal + * physics_variables.p_plasma_rad_mw + / physics_variables.a_plasma_surface + ) + else: + if heat_transport_variables.ipowerflow == 0: + physics_variables.pflux_fw_rad_mw = ( + (1.0e0 - fwbs_variables.fhole) + * physics_variables.p_plasma_rad_mw + / build_variables.a_fw_total + ) + else: + physics_variables.pflux_fw_rad_mw = ( + ( + 1.0e0 + - fwbs_variables.fhole + - fwbs_variables.f_a_fw_outboard_hcd + - fwbs_variables.f_ster_div_single + ) + * physics_variables.p_plasma_rad_mw + / build_variables.a_fw_total + ) + + constraint_variables.pflux_fw_rad_max_mw = ( + physics_variables.pflux_fw_rad_mw * constraint_variables.f_fw_rad_max + ) + + physics_variables.rad_fraction_total = physics_variables.p_plasma_rad_mw / ( + physics_variables.f_p_alpha_plasma_deposited + * physics_variables.p_alpha_total_mw + + physics_variables.p_non_alpha_charged_mw + + physics_variables.p_plasma_ohmic_mw + + current_drive_variables.p_hcd_injected_total_mw + ) + + # Calculate transport losses and energy confinement time using the + # chosen scaling law + # N.B. stellarator_variables.iotabar replaces tokamak physics_variables.q95 in argument list + + ( + physics_variables.pden_electron_transport_loss_mw, + physics_variables.pden_ion_transport_loss_mw, + physics_variables.t_electron_energy_confinement, + physics_variables.t_ion_energy_confinement, + physics_variables.t_energy_confinement, + physics_variables.p_plasma_loss_mw, + ) = self.physics.calculate_confinement_time( + physics_variables.m_fuel_amu, + physics_variables.p_alpha_total_mw, + physics_variables.aspect, + physics_variables.b_plasma_toroidal_on_axis, + physics_variables.nd_plasma_ions_total_vol_avg, + physics_variables.nd_plasma_electrons_vol_avg, + physics_variables.nd_plasma_electron_line, + physics_variables.eps, + physics_variables.hfact, + physics_variables.i_confinement_time, + physics_variables.i_plasma_ignited, + physics_variables.kappa, + physics_variables.kappa95, + physics_variables.p_non_alpha_charged_mw, + current_drive_variables.p_hcd_injected_total_mw, + physics_variables.plasma_current, + physics_variables.pden_plasma_core_rad_mw, + physics_variables.rmajor, + physics_variables.rminor, + physics_variables.temp_plasma_electron_density_weighted_kev, + physics_variables.temp_plasma_ion_density_weighted_kev, + stellarator_variables.iotabar, + physics_variables.qstar, + physics_variables.vol_plasma, + physics_variables.n_charge_plasma_effective_vol_avg, + ) + + physics_variables.p_electron_transport_loss_mw = ( + physics_variables.pden_electron_transport_loss_mw + * physics_variables.vol_plasma + ) + physics_variables.p_ion_transport_loss_mw = ( + physics_variables.pden_ion_transport_loss_mw * physics_variables.vol_plasma + ) + + physics_variables.pscalingmw = ( + physics_variables.p_electron_transport_loss_mw + + physics_variables.p_ion_transport_loss_mw + ) + + # Calculate auxiliary physics related information + # for the rest of the code + + sbar = 1.0e0 + ( + physics_variables.burnup, + physics_variables.ntau, + physics_variables.nTtau, + physics_variables.figmer, + _fusrat, + physics_variables.molflow_plasma_fuelling_required, + physics_variables.rndfuel, + physics_variables.t_alpha_confinement, + physics_variables.f_alpha_energy_confinement, + ) = self.physics.phyaux( + physics_variables.aspect, + physics_variables.nd_plasma_electrons_vol_avg, + physics_variables.temp_plasma_electron_vol_avg_kev, + physics_variables.nd_plasma_fuel_ions_vol_avg, + physics_variables.fusden_total, + physics_variables.fusden_alpha_total, + physics_variables.plasma_current, + sbar, + physics_variables.nd_plasma_alphas_vol_avg, + physics_variables.t_energy_confinement, + physics_variables.vol_plasma, + ) + + # Calculate the neoclassical sanity check with PROCESS parameters + ( + q_PROCESS, + q_PROCESS_r1, + _q_neo, + _gamma_neo, + _total_q_neo, + total_q_neo_e, + q_neo_e, + _q_neo_D, + _q_neo_a, + _q_neo_T, + g_neo_e, + _g_neo_D, + _g_neo_a, + _g_neo_T, + dndt_neo_e, + _dndt_neo_D, + _dndt_neo_a, + _dndt_neo_T, + _dndt_neo_fuel, + _dmdt_neo_fuel, + dmdt_neo_fuel_from_e, + chi_neo_e, + chi_PROCESS_e, + nu_star_e, + nu_star_d, + nu_star_T, + nu_star_He, + ) = self.neoclassics.calc_neoclassics() + + if output: + self.st_phys_output( + q_PROCESS, + total_q_neo_e, + dmdt_neo_fuel_from_e, + q_PROCESS_r1, + chi_PROCESS_e, + chi_neo_e, + q_neo_e, + g_neo_e, + dndt_neo_e, + physics_variables.rho_ne_max, + physics_variables.rho_te_max, + physics_variables.gradient_length_ne, + physics_variables.gradient_length_te, + physics_variables.rho_star, + nu_star_e, + nu_star_d, + nu_star_T, + nu_star_He, + physics_variables.nd_plasma_electron_line, + physics_variables.nd_plasma_electrons_max, + ) + + def st_phys_output( + self, + q_PROCESS, + total_q_neo_e, + dmdt_neo_fuel_from_e, + q_PROCESS_r1, + chi_PROCESS_e, + chi_neo_e, + q_neo_e, + g_neo_e, + dndt_neo_e, + rho_ne_max, + rho_te_max, + gradient_length_ne, + gradient_length_te, + rho_star, + nu_star_e, + nu_star_D, + nu_star_T, + nu_star_He, + nd_plasma_electron_line, + nd_plasma_electrons_max, + ): + po.oheadr(self.outfile, "Stellarator Specific Physics:") + + po.ovarre( + self.outfile, + "Total 0D heat flux (r=rhocore) (MW/m2)", + "(q_PROCESS)", + q_PROCESS, + ) + po.ovarre( + self.outfile, + "Total neoclassical flux from 4*q_e (r=rhocore) (MW/m2)", + "(total_q_neo_e)", + total_q_neo_e, + ) + + po.ovarre( + self.outfile, + "Total fuel (DT) mass flux by using 4 * neoclassical e transport (mg/s): ", + "(dmdt_neo_fuel_from_e)", + dmdt_neo_fuel_from_e, + ) + po.ovarre( + self.outfile, + "Considered Heatflux by LCFS heat flux ratio (1)", + "(q_PROCESS/q_PROCESS_r1)", + q_PROCESS / q_PROCESS_r1, + ) + + po.ovarre( + self.outfile, + "Resulting electron effective chi (0D) (r=rhocore): ", + "(chi_PROCESS_e)", + chi_PROCESS_e, + ) + po.ovarre( + self.outfile, + "Neoclassical electron effective chi (r=rhocore): ", + "(chi_neo_e)", + chi_neo_e, + ) + + po.ovarre( + self.outfile, + "Heat flux due to neoclassical energy transport (e) (MW/m2): ", + "(q_neo_e)", + q_neo_e, + ) + po.ovarre( + self.outfile, + "Heat flux due to neoclassical particle transport (e) (MW/m2): ", + "(g_neo_e)", + g_neo_e, + ) + po.ovarre( + self.outfile, + "Particle flux due to neoclassical particle transport (e) (1/m2/s): ", + "(dndt_neo_e)", + dndt_neo_e, + ) + + po.ovarre( + self.outfile, "r/a of maximum ne gradient (m)", "(rho_ne_max)", rho_ne_max + ) + po.ovarre( + self.outfile, "r/a of maximum te gradient (m)", "(rho_te_max)", rho_te_max + ) + po.ovarre( + self.outfile, + "Maxium ne gradient length (1)", + "(gradient_length_ne)", + gradient_length_ne, + ) + po.ovarre( + self.outfile, + "Maxium te gradient length (1)", + "(gradient_length_te)", + gradient_length_te, + ) + po.ovarre( + self.outfile, + "Gradient Length Ratio (T/n) (1)", + "(gradient_length_ratio)", + gradient_length_te / gradient_length_ne, + ) + + po.ovarre(self.outfile, "Normalized ion Larmor radius", "(rho_star)", rho_star) + po.ovarre( + self.outfile, + "Normalized collisionality (electrons)", + "(nu_star_e)", + nu_star_e, + ) + po.ovarre( + self.outfile, "Normalized collisionality (D)", "(nu_star_D)", nu_star_D + ) + po.ovarre( + self.outfile, "Normalized collisionality (T)", "(nu_star_T)", nu_star_T + ) + po.ovarre( + self.outfile, "Normalized collisionality (He)", "(nu_star_He)", nu_star_He + ) + + po.ovarre( + self.outfile, + "Obtained line averaged density at op. point (/m3)", + "(nd_plasma_electron_line)", + nd_plasma_electron_line, + ) + po.ovarre( + self.outfile, + "Sudo density limit (/m3)", + "(nd_plasma_electrons_max)", + nd_plasma_electrons_max, + ) + po.ovarre( + self.outfile, + "Ratio density to sudo limit (1)", + "(nd_plasma_electron_line/nd_plasma_electrons_max)", + nd_plasma_electron_line / nd_plasma_electrons_max, + ) diff --git a/pyproject.toml b/pyproject.toml index d5086f9266..2fc29b7a63 100644 --- a/pyproject.toml +++ b/pyproject.toml @@ -226,4 +226,5 @@ ignore-names = [ "Kr", "Xe", "W", + "*W7X*", ] diff --git a/tests/regression/input_files/helias_5b.IN.DAT b/tests/regression/input_files/helias_5b.IN.DAT index 1c048c9d64..4122e50d6f 100644 --- a/tests/regression/input_files/helias_5b.IN.DAT +++ b/tests/regression/input_files/helias_5b.IN.DAT @@ -50,12 +50,11 @@ i_plasma_ignited = 1 *Switch for ignition assumption (1: Ignited) i_plasma_pedestal = 0 *Switch for pedestal profiles (0: Parabolic Profiles) i_rad_loss = 1 *Switch for radiation loss term usage in power balance (1: Total power lost is scaling power plus core radiation only) i_confinement_time = 38 *Switch for energy confinement time scaling law (38: ISS04) -kappa = 1.001 *Plasma separatrix elongation rmajor = 22.0 *Plasma major radius (m) f_sync_reflect = 0.6 *Synchrotron wall reflectivity factor temp_plasma_electron_vol_avg_kev = 7.0 *Volume averaged electron temperature (keV) f_temp_plasma_ion_electron = 0.95 *Ion temperature / electron temperature -*zfear = 0 *High-Z impurity switch (0: Iron) + *--------------Stellarator Variables---------------* @@ -169,15 +168,6 @@ f_a_tf_turn_cable_space_extra_void = 0.3 *Coolant fraction of TF co dr_tf_nose_case = 0.06 * Case thickness *-----------------Pfcoil Variables-----------------* -*PF coil vertical positioning adjuster -zref(1) = 3.6 -zref(2) = 1.2 -zref(3) = 2.5 -zref(4) = 1.0 -zref(5) = 1.0 -zref(6) = 1.0 -zref(7) = 1.0 -zref(8) = 1.0 *------------------Cost Variables------------------* cost_model = 0 *0: 1990 cost module, the 2015 does not work yet for stellarators diff --git a/tests/unit/test_neoclassics.py b/tests/unit/test_neoclassics.py index 8dcf933e6a..f220216d95 100644 --- a/tests/unit/test_neoclassics.py +++ b/tests/unit/test_neoclassics.py @@ -4,7 +4,7 @@ import pytest from process.data_structure import neoclassics_variables, physics_variables -from process.stellarator import Neoclassics +from process.stellarator.neoclassics import Neoclassics @pytest.fixture diff --git a/tests/unit/test_stellarator.py b/tests/unit/test_stellarator.py index d325577c28..af8ff03bfb 100644 --- a/tests/unit/test_stellarator.py +++ b/tests/unit/test_stellarator.py @@ -31,7 +31,14 @@ from process.physics import Physics from process.plasma_profiles import PlasmaProfile from process.power import Power -from process.stellarator import Neoclassics, Stellarator +from process.stellarator.coils.coils import bmax_from_awp, intersect +from process.stellarator.coils.quench import ( + calculate_quench_protection_current_density, + max_dump_voltage, +) +from process.stellarator.denisty_limits import st_d_limit_ecrh +from process.stellarator.neoclassics import Neoclassics +from process.stellarator.stellarator import Stellarator from process.vacuum import Vacuum @@ -94,9 +101,9 @@ class StgeomParam(NamedTuple): stella_config_plasma_surface: Any = None - f_r: Any = None + f_st_r: Any = None - f_a: Any = None + f_st_rminor: Any = None expected_a_plasma_surface: Any = None @@ -121,8 +128,8 @@ class StgeomParam(NamedTuple): b_plasma_toroidal_on_axis=5.5, stella_config_vol_plasma=1422.6300000000001, stella_config_plasma_surface=1960, - f_r=0.99099099099099097, - f_a=0.99125889880147788, + f_st_r=0.99099099099099097, + f_st_rminor=0.99125889880147788, expected_a_plasma_surface=1925.3641313657533, expected_a_plasma_surface_outboard=962.68206568287667, expected_vol=1385.2745877380669, @@ -139,8 +146,8 @@ class StgeomParam(NamedTuple): b_plasma_toroidal_on_axis=5.5, stella_config_vol_plasma=1422.6300000000001, stella_config_plasma_surface=1960, - f_r=0.99099099099099097, - f_a=0.99125889880147788, + f_st_r=0.99099099099099097, + f_st_rminor=0.99125889880147788, expected_a_plasma_surface=1925.3641313657533, expected_a_plasma_surface_outboard=962.68206568287667, expected_vol=1385.2745877380669, @@ -201,9 +208,9 @@ def test_stgeom(stgeomparam, monkeypatch, stellarator): stgeomparam.stella_config_plasma_surface, ) - monkeypatch.setattr(stellarator_variables, "f_r", stgeomparam.f_r) + monkeypatch.setattr(stellarator_variables, "f_st_rmajor", stgeomparam.f_st_rmajor) - monkeypatch.setattr(stellarator_variables, "f_a", stgeomparam.f_a) + monkeypatch.setattr(stellarator_variables, "f_st_rminor", stgeomparam.f_st_rminor) stellarator.stgeom() @@ -319,11 +326,11 @@ class StbildParam(NamedTuple): stella_config_min_plasma_coil_distance: Any = None - f_r: Any = None + f_st_rmajor: Any = None - f_aspect: Any = None + f_st_aspect: Any = None - f_a: Any = None + f_st_rminor: Any = None iprint: Any = None @@ -410,9 +417,9 @@ class StbildParam(NamedTuple): stella_config_derivative_min_lcfs_coils_dist=-1, stella_config_rminor_ref=1.8, stella_config_min_plasma_coil_distance=1.8999999999999999, - f_r=0.99099099099099097, - f_aspect=1, - f_a=0.99125889880147788, + f_st_rmajor=0.99099099099099097, + f_st_aspect=1, + f_st_rminor=0.99125889880147788, iprint=0, outfile=11, expected_dz_blkt_upper=0.75, @@ -479,9 +486,9 @@ class StbildParam(NamedTuple): stella_config_derivative_min_lcfs_coils_dist=-1, stella_config_rminor_ref=1.8, stella_config_min_plasma_coil_distance=1.8999999999999999, - f_r=0.99099099099099097, - f_aspect=1, - f_a=0.99125889880147788, + f_st_rmajor=0.99099099099099097, + f_st_aspect=1, + f_st_rminor=0.99125889880147788, iprint=0, outfile=11, expected_dz_blkt_upper=0.75, @@ -658,11 +665,11 @@ def test_stbild(stbildparam, monkeypatch, stellarator): stbildparam.stella_config_min_plasma_coil_distance, ) - monkeypatch.setattr(stellarator_variables, "f_r", stbildparam.f_r) + monkeypatch.setattr(stellarator_variables, "f_st_rmajor", stbildparam.f_st_rmajor) - monkeypatch.setattr(stellarator_variables, "f_aspect", stbildparam.f_aspect) + monkeypatch.setattr(stellarator_variables, "f_st_aspect", stbildparam.f_st_aspect) - monkeypatch.setattr(stellarator_variables, "f_a", stbildparam.f_a) + monkeypatch.setattr(stellarator_variables, "f_st_rminor", stbildparam.f_st_rminor) stellarator.stbild(False) assert build_variables.dz_blkt_upper == pytest.approx( @@ -741,11 +748,11 @@ class StstrcParam(NamedTuple): stella_config_coillength: Any = None - f_n: Any = None + f_st_n_coils: Any = None - f_r: Any = None + f_st_rmajor: Any = None - f_b: Any = None + f_st_b: Any = None iprint: Any = None @@ -776,9 +783,9 @@ class StstrcParam(NamedTuple): dx_tf_inboard_out_toroidal=0.67648706726464258, stella_config_coilsurface=4817.6999999999998, stella_config_coillength=1680, - f_n=1, - f_r=0.99099099099099097, - f_b=0.98214285714285721, + f_st_n_coils=1, + f_st_rmajor=0.99099099099099097, + f_st_b=0.98214285714285721, iprint=0, outfile=11, expected_aintmass=4882304.266547408, @@ -800,9 +807,9 @@ class StstrcParam(NamedTuple): dx_tf_inboard_out_toroidal=0.67648706726464258, stella_config_coilsurface=4817.6999999999998, stella_config_coillength=1680, - f_n=1, - f_r=0.99099099099099097, - f_b=0.98214285714285721, + f_st_n_coils=1, + f_st_rmajor=0.99099099099099097, + f_st_b=0.98214285714285721, iprint=0, outfile=11, expected_aintmass=4882304.266547408, @@ -874,11 +881,11 @@ def test_ststrc(ststrcparam, monkeypatch, stellarator): ststrcparam.stella_config_coillength, ) - monkeypatch.setattr(stellarator_variables, "f_n", ststrcparam.f_n) + monkeypatch.setattr(stellarator_variables, "f_st_n_coils", ststrcparam.f_st_n_coils) - monkeypatch.setattr(stellarator_variables, "f_r", ststrcparam.f_r) + monkeypatch.setattr(stellarator_variables, "f_st_rmajor", ststrcparam.f_st_rmajor) - monkeypatch.setattr(stellarator_variables, "f_b", ststrcparam.f_b) + monkeypatch.setattr(stellarator_variables, "f_st_b", ststrcparam.f_st_b) stellarator.ststrc(False) @@ -889,29 +896,29 @@ def test_ststrc(ststrcparam, monkeypatch, stellarator): assert structure_variables.coldmass == pytest.approx(ststrcparam.expected_coldmass) -def test_u_max_protect_v(stellarator): - assert stellarator.u_max_protect_v( - tfes=2651198129.2530489, tdump=10, aio=122620.32643505408 +def test_u_max_protect_v(): + assert max_dump_voltage( + tf_energy_stored=2651198129.2530489, t_dump=10, current=122620.32643505408 ) == pytest.approx(4324.2392290600483) -def test_j_max_protect_am2(stellarator): - assert stellarator.j_max_protect_am2( +def test_j_max_protect_am2(): + assert calculate_quench_protection_current_density( tau_quench=10, t_detect=0, - fcu=0.69000000000000017, - fcond=0.69999999999999996, + f_cu=0.69000000000000017, + f_cond=0.69999999999999996, temp=4.2000000000000002, - acs=0.0022141440000000008, - aturn=0.0031360000000000008, + a_cable=0.0022141440000000008, + a_turn=0.0031360000000000008, ) == pytest.approx(54919989.379449144) -def test_bmax_from_awp(stellarator, monkeypatch): +def test_bmax_from_awp(monkeypatch): monkeypatch.setattr(stellarator_configuration, "stella_config_a1", 0.688) monkeypatch.setattr(stellarator_configuration, "stella_config_a2", 0.025) - assert stellarator.bmax_from_awp( + assert bmax_from_awp( wp_width_radial=0.11792792792792792, current=12.711229086229087, n_tf_coils=50, @@ -2599,7 +2606,7 @@ class IntersectParam(NamedTuple): ), ), ) -def test_intersect(intersectparam, stellarator): +def test_intersect(intersectparam): """ Automatically generated Regression Unit Test for intersect. @@ -2609,7 +2616,7 @@ def test_intersect(intersectparam, stellarator): :type intersectparam: intersectparam """ - x = stellarator.intersect( + x = intersect( x1=intersectparam.x1, y1=intersectparam.y1, x2=intersectparam.x2, @@ -2698,7 +2705,7 @@ def test_stdlim(stdlimparam, monkeypatch, stellarator): stdlimparam.nd_plasma_electrons_max, ) - nd_plasma_electron_max_array = stellarator.stdlim( + nd_plasma_electron_max_array = stellarator.st_sudo_density_limit( b_plasma_toroidal_on_axis=stdlimparam.b_plasma_toroidal_on_axis, powht=stdlimparam.powht, rmajor=stdlimparam.rmajor, @@ -2736,7 +2743,7 @@ class StdlimEcrhParam(NamedTuple): ), ), ) -def test_stdlim_ecrh(stdlimecrhparam, monkeypatch, stellarator): +def test_stdlim_ecrh(stdlimecrhparam, monkeypatch): """ Automatically generated Regression Unit Test for stdlim_ecrh. @@ -2753,7 +2760,7 @@ def test_stdlim_ecrh(stdlimecrhparam, monkeypatch, stellarator): physics_variables, "i_plasma_pedestal", stdlimecrhparam.i_plasma_pedestal ) - dlimit_ecrh, bt_max = stellarator.stdlim_ecrh( + dlimit_ecrh, bt_max = st_d_limit_ecrh( bt_input=stdlimecrhparam.bt_input, gyro_frequency_max=stdlimecrhparam.gyro_frequency_max, ) @@ -2787,7 +2794,7 @@ class StCalcEffChiParam(NamedTuple): stella_config_rminor_ref: Any = None - f_r: Any = None + f_st_rmajor: Any = None expected_output: Any = None @@ -2808,7 +2815,7 @@ class StCalcEffChiParam(NamedTuple): rminor=1.7863900994187722, radius_plasma_core_norm=0.60000000000000009, stella_config_rminor_ref=1.80206932, - f_r=0.99129932482229, + f_st_rmajor=0.99129932482229, expected_output=0.2620230359599852, # expected_output=0.26206561772729992, used old e_ ), @@ -2825,7 +2832,7 @@ class StCalcEffChiParam(NamedTuple): rminor=1.7863900994187722, radius_plasma_core_norm=0.60000000000000009, stella_config_rminor_ref=1.80206932, - f_r=0.99129932482229, + f_st_rmajor=0.99129932482229, expected_output=0.2368034193234161, # expected_output=0.23684190261197124, used old e_ ), @@ -2898,7 +2905,9 @@ def test_st_calc_eff_chi(stcalceffchiparam, monkeypatch, stellarator): stcalceffchiparam.stella_config_rminor_ref, ) - monkeypatch.setattr(stellarator_variables, "f_r", stcalceffchiparam.f_r) + monkeypatch.setattr( + stellarator_variables, "f_st_rmajor", stcalceffchiparam.f_st_rmajor + ) output = stellarator.st_calc_eff_chi() @@ -3058,7 +3067,7 @@ def test_sctfcoil_nuclear_heating_iter90( ptfowp, raddose, p_tf_nuclear_heat_mw, - ) = stellarator.sctfcoil_nuclear_heating_iter90() + ) = stellarator.sc_tf_coil_nuclear_heating_iter90() assert coilhtmx == pytest.approx(sctfcoilnuclearheatingiter90param.expected_coilhtmx) assert dpacop == pytest.approx(sctfcoilnuclearheatingiter90param.expected_dpacop)