def make_firstwall_material(firstwall_armour_material,
firstwall_armour_fraction,
firstwall_coolant_material,
firstwall_coolant_fraction,
firstwall_structural_material,
firstwall_structural_fraction):
if firstwall_coolant_material == 'He':
temperature_in_C = 400
pressure_in_Pa = 8e6
elif firstwall_coolant_material in ['H2O', 'D2O']:
temperature_in_C = 305
pressure_in_Pa = 15.5e6
firstwall_material = MultiMaterial(
material_name='firstwall_material',
materials=[
Material(material_name=firstwall_armour_material),
Material(material_name=firstwall_coolant_material,
temperature_in_C=temperature_in_C,
pressure_in_Pa=pressure_in_Pa),
Material(material_name=firstwall_structural_material)
],
fracs=[
firstwall_armour_fraction, firstwall_coolant_fraction,
firstwall_structural_fraction
]).neutronics_material
return firstwall_material
def make_blanket_material(
blanket_structural_material, blanket_structural_fraction,
blanket_coolant_material, blanket_coolant_fraction,
blanket_multiplier_material, blanket_multiplier_fraction,
blanket_breeder_material, blanket_breeder_fraction,
blanket_breeder_li6_enrichment_fraction,
blanket_breeder_packing_fraction, blanket_multiplier_packing_fraction):
if blanket_coolant_material == 'He':
temperature_in_C = 400
pressure_in_Pa = 8e6
elif blanket_coolant_material in ['H2O', 'D2O']:
temperature_in_C = 305
pressure_in_Pa = 15.5e6
blanket_material = MultiMaterial(
material_name='blanket_material',
materials=[
Material(material_name=blanket_structural_material),
Material(material_name=blanket_coolant_material,
temperature_in_C=temperature_in_C,
pressure_in_Pa=pressure_in_Pa),
Material(material_name=blanket_multiplier_material,
packing_fraction=blanket_multiplier_packing_fraction),
Material(
material_name=blanket_breeder_material,
enrichment_fraction=blanket_breeder_li6_enrichment_fraction,
temperature_in_C=500,
packing_fraction=blanket_breeder_packing_fraction),
],
fracs=[
blanket_structural_fraction, blanket_coolant_fraction,
blanket_multiplier_fraction, blanket_breeder_fraction
],
percent_type='vo').neutronics_material
return blanket_material
def make_neutronics_model(
reactor,
firstwall_radial_thickness,
firstwall_armour_material,
firstwall_coolant_material,
firstwall_structural_material,
firstwall_armour_fraction,
firstwall_coolant_fraction,
firstwall_coolant_temperature_C,
firstwall_coolant_pressure_Pa,
firstwall_structural_fraction,
blanket_rear_wall_coolant_material,
blanket_rear_wall_structural_material,
blanket_rear_wall_coolant_fraction,
blanket_rear_wall_structural_fraction,
blanket_rear_wall_coolant_temperature_C,
blanket_rear_wall_coolant_pressure_Pa,
blanket_lithium6_enrichment_percent,
blanket_breeder_material,
blanket_coolant_material,
blanket_multiplier_material,
blanket_structural_material,
blanket_breeder_fraction,
blanket_coolant_fraction,
blanket_multiplier_fraction,
blanket_structural_fraction,
blanket_breeder_packing_fraction,
blanket_multiplier_packing_fraction,
blanket_coolant_temperature_C,
blanket_coolant_pressure_Pa,
blanket_breeder_temperature_C,
blanket_breeder_pressure_Pa,
divertor_coolant_fraction,
divertor_structural_fraction,
divertor_coolant_material,
divertor_structural_material,
divertor_coolant_temperature_C,
divertor_coolant_pressure_Pa,
center_column_shield_coolant_fraction,
center_column_shield_structural_fraction,
center_column_shield_coolant_material,
center_column_shield_structural_material,
center_column_shield_coolant_temperature_C,
center_column_shield_coolant_pressure_Pa,
inboard_tf_coils_conductor_fraction,
inboard_tf_coils_coolant_fraction,
inboard_tf_coils_structure_fraction,
inboard_tf_coils_conductor_material,
inboard_tf_coils_coolant_material,
inboard_tf_coils_structure_material,
inboard_tf_coils_coolant_temperature_C,
inboard_tf_coils_coolant_pressure_Pa,
):
"""
Makes and runs a simple OpenMC neutronics model with
the materials with the same tags as the DAGMC neutronics
geometry. The model also specifies the computational
intensity (particles and batches) and the tally to record
"""
input_parameters = locals()
# this is the underlying geometry container that is filled with the faceteted CAD model
universe = openmc.Universe()
geom = openmc.Geometry(universe)
center_column_shield_material = MultiMaterial(
material_tag='center_column_shield_mat',
materials=[
Material(
material_name=center_column_shield_coolant_material,
temperature_in_C=center_column_shield_coolant_temperature_C,
pressure_in_Pa=center_column_shield_coolant_pressure_Pa),
Material(material_name=center_column_shield_structural_material)
],
fracs=[
center_column_shield_coolant_fraction,
center_column_shield_structural_fraction
],
percent_type='vo',
packing_fraction=1.0).openmc_material
firstwall_material = MultiMaterial(
material_tag='firstwall_mat',
materials=[
Material(material_name=firstwall_coolant_material,
temperature_in_C=firstwall_coolant_temperature_C,
pressure_in_Pa=firstwall_coolant_pressure_Pa),
Material(material_name=firstwall_structural_material),
Material(material_name=firstwall_armour_material)
],
fracs=[
firstwall_coolant_fraction, firstwall_structural_fraction,
firstwall_armour_fraction
],
percent_type='vo',
packing_fraction=1.0).openmc_material
if blanket_multiplier_material == None and blanket_multiplier_fraction == None and blanket_multiplier_packing_fraction == None:
blanket_material = MultiMaterial(
material_tag='blanket_mat',
materials=[
Material(material_name=blanket_coolant_material,
temperature_in_C=blanket_coolant_temperature_C,
pressure_in_Pa=blanket_coolant_pressure_Pa),
Material(material_name=blanket_structural_material),
Material(material_name=blanket_breeder_material,
enrichment=blanket_lithium6_enrichment_percent,
packing_fraction=blanket_breeder_packing_fraction,
temperature_in_C=blanket_breeder_temperature_C,
pressure_in_Pa=blanket_breeder_pressure_Pa)
],
fracs=[
blanket_coolant_fraction, blanket_structural_fraction,
blanket_breeder_fraction
],
percent_type='vo',
packing_fraction=1.0).openmc_material
else:
blanket_material = MultiMaterial(
material_tag='blanket_mat',
materials=[
Material(material_name=blanket_coolant_material,
temperature_in_C=blanket_coolant_temperature_C,
pressure_in_Pa=blanket_coolant_pressure_Pa),
Material(material_name=blanket_structural_material),
Material(material_name=blanket_multiplier_material,
packing_fraction=blanket_multiplier_packing_fraction),
Material(material_name=blanket_breeder_material,
enrichment=blanket_lithium6_enrichment_percent,
packing_fraction=blanket_breeder_packing_fraction,
temperature_in_C=blanket_breeder_temperature_C,
pressure_in_Pa=blanket_breeder_pressure_Pa)
],
fracs=[
blanket_coolant_fraction, blanket_structural_fraction,
blanket_multiplier_fraction, blanket_breeder_fraction
],
percent_type='vo',
packing_fraction=1.0).openmc_material
divertor_material = MultiMaterial(
material_tag='divertor_mat',
materials=[
Material(material_name=divertor_coolant_material,
temperature_in_C=divertor_coolant_temperature_C,
pressure_in_Pa=divertor_coolant_pressure_Pa),
Material(material_name=divertor_structural_material)
],
fracs=[divertor_coolant_fraction, divertor_structural_fraction],
percent_type='vo',
packing_fraction=1.0).openmc_material
inboard_tf_coils_material = MultiMaterial(
material_tag='inboard_tf_coils_mat',
materials=[
Material(material_name=inboard_tf_coils_coolant_material,
temperature_in_C=inboard_tf_coils_coolant_temperature_C,
pressure_in_Pa=inboard_tf_coils_coolant_pressure_Pa),
Material(material_name=inboard_tf_coils_conductor_material),
Material(material_name=inboard_tf_coils_structure_material)
],
fracs=[
inboard_tf_coils_coolant_fraction,
inboard_tf_coils_conductor_fraction,
inboard_tf_coils_structure_fraction
],
percent_type='vo',
packing_fraction=1.0).openmc_material
blanket_rear_wall_material = MultiMaterial(
material_tag='blanket_rear_wall_mat',
materials=[
Material(material_name=blanket_rear_wall_coolant_material,
temperature_in_C=blanket_rear_wall_coolant_temperature_C,
pressure_in_Pa=blanket_rear_wall_coolant_pressure_Pa),
Material(material_name=blanket_rear_wall_structural_material)
],
fracs=[
blanket_rear_wall_coolant_fraction,
blanket_rear_wall_structural_fraction
],
percent_type='vo',
packing_fraction=1.0).openmc_material
mats = openmc.Materials([
center_column_shield_material, firstwall_material, blanket_material,
divertor_material, inboard_tf_coils_material,
blanket_rear_wall_material
])
# settings for the number of neutrons to simulate
settings = openmc.Settings()
settings.batches = 10
settings.inactive = 0
settings.particles = 1000
settings.run_mode = 'fixed source'
settings.dagmc = True
# details of the birth locations and energy of the neutronis
source = openmc.Source()
source.space = openmc.stats.Point((reactor['major_radius'], 0, 0))
source.angle = openmc.stats.Isotropic()
source.energy = openmc.stats.Discrete([14e6], [1])
settings.source = source
settings.photon_transport = True # This line is required to switch on photons tracking
# details about what neutrons interactions to keep track of (called a tally)
tallies = openmc.Tallies()
material_filter = openmc.MaterialFilter(blanket_material)
tbr_tally = openmc.Tally(name='TBR')
tbr_tally.filters = [material_filter]
tbr_tally.scores = ['(n,Xt)'] # where X is a wild card
tallies.append(tbr_tally)
material_filter = openmc.MaterialFilter(
[blanket_material, firstwall_material, blanket_rear_wall_material])
blanket_heating_tally = openmc.Tally(name='blanket_heating')
blanket_heating_tally.filters = [material_filter]
blanket_heating_tally.scores = ['heating']
tallies.append(blanket_heating_tally)
# make the model from gemonetry, materials, settings and tallies
model = openmc.model.Model(geom, mats, settings, tallies)
# run the simulation
output_filename = model.run()
"""
Reads the output file from the neutronics simulation
and prints the TBR tally result to screen
"""
# open the results file
sp = openmc.StatePoint(output_filename)
# access TBR tally
tbr_tally = sp.get_tally(name='TBR')
df = tbr_tally.get_pandas_dataframe()
tbr_tally_result = df['mean'].sum()
tbr_tally_std_dev = df['std. dev.'].sum()
# access heating tally
blanket_heating_tally = sp.get_tally(name='blanket_heating')
df = blanket_heating_tally.get_pandas_dataframe()
blanket_heating_tally_result = df['mean'].sum() / 1e6
blanket_heating_tally_std_dev = df['std. dev.'].sum() / 1e6
# returns all the inputs and some extra reactor attributes, merged into a single dictionary
return {
**input_parameters,
**{
'tbr': tbr_tally_result,
'tbr_std_dev': tbr_tally_std_dev,
'blanket_heating': blanket_heating_tally_result,
'blanket_heating_std_dev': blanket_heating_tally_std_dev,
}
}
import openmc
import numpy as np
import plotly.graph_objs as go
from neutronics_material_maker import Material, MultiMaterial
# Homogeneous mixture of helium and Li4SiO4 using MultiMaterial class
# MultiMaterial class requires list of Material objects to be passed
helium = Material('He', temperature_in_C=500, pressure_in_Pa=100000)
Li4SiO4 = Material('Li4SiO4', enrichment=60)
mixed_helium_Li4SiO4 = MultiMaterial(
material_name='mixed_helium_Li4SiO4', # name of homogeneous material
materials=[helium,
Li4SiO4], # list of material objects (NOT neutronics materials)
fracs=[0.36,
0.64], # list of combination fractions for each material object
percent_type='vo') # combination fraction type
# print(mixed_helium_Li4SiO4.neutronics_material)
# Homogenous mixture of tungsten carbide and water using mix_materials function
mixed_water_WC = openmc.Material.mix_materials(
name='mixed_water_WC', # name of homogeneous material
materials=[ # list of neutronics materials
Material('WC').neutronics_material,
Material('H2O', temperature_in_C=25,
pressure_in_Pa=100000).neutronics_material
],
fracs=[0.8,
0.2], # list of combination fractions for each neutronics material
def find_tbr_from_graded_blanket(
number_of_layers, layer_thickness_fractions, layer_li6_enrichments,
layer_breeder_fractions, layer_multiplier_fractions,
blanket_structural_material, blanket_multiplier_material,
blanket_breeder_material, firstwall_coolant,
blanket_structural_fraction, inner_radius, thickness,
firstwall_thickness):
batches = 10
thickness_fraction_scaler = thickness / sum(layer_thickness_fractions)
print('thickness_fraction_scaler', thickness_fraction_scaler)
if firstwall_coolant == 'no firstwall':
breeder_blanket_inner_surface = openmc.Sphere(r=inner_radius)
inner_void_region = -breeder_blanket_inner_surface
inner_void_cell = openmc.Cell(region=inner_void_region)
inner_void_cell.name = 'inner_void'
surfaces = [breeder_blanket_inner_surface]
additional_thickness = 0
all_layers_materials = []
all_cells = [inner_void_cell]
for i, (layer_thickness, layer_enrichment, layer_breeder_fraction,
layer_multiplier_fraction) in enumerate(
zip(layer_thickness_fractions, layer_li6_enrichments,
layer_breeder_fractions, layer_multiplier_fractions)):
print(i, layer_thickness, layer_enrichment, layer_breeder_fraction)
layer_material = MultiMaterial(
material_name='layer_' + str(i) + '_material',
materials=[
Material(blanket_breeder_material,
enrichment_fraction=layer_enrichment),
Material(blanket_multiplier_material),
Material(blanket_structural_material)
],
fracs=[
layer_breeder_fraction, layer_multiplier_fraction,
blanket_structural_fraction
]).neutronics_material
all_layers_materials.append(layer_material)
additional_thickness = additional_thickness + (
layer_thickness * thickness_fraction_scaler)
print('additional_thickness', additional_thickness)
if i == number_of_layers - 1:
layer_outer_surface = openmc.Sphere(r=inner_radius +
additional_thickness,
boundary_type='vacuum')
else:
layer_outer_surface = openmc.Sphere(r=inner_radius +
additional_thickness)
layer_inner_surface = surfaces[-1]
layer_region = -layer_outer_surface & +layer_inner_surface
layer_cell = openmc.Cell(region=layer_region)
layer_cell.fill = layer_material
layer_cell.name = 'layer_' + str(i) + '_cell'
surfaces.append(layer_outer_surface)
all_cells.append(layer_cell)
else:
#firstwall is present
firstwall_material = MultiMaterial(
material_name='firstwall_material',
materials=[
Material('tungsten'),
Material(firstwall_coolant),
Material(blanket_structural_material)
],
fracs=[0.055262, 0.253962,
0.690776] #based on HCPB paper with 2mm W firstwall
).neutronics_material
breeder_blanket_inner_surface = openmc.Sphere(r=inner_radius +
firstwall_thickness)
firstwall_outer_surface = openmc.Sphere(r=inner_radius)
surfaces = [firstwall_outer_surface, breeder_blanket_inner_surface]
inner_void_region = -firstwall_outer_surface
inner_void_cell = openmc.Cell(region=inner_void_region)
inner_void_cell.name = 'inner_void'
firstwall_region = +firstwall_outer_surface & -breeder_blanket_inner_surface
firstwall_cell = openmc.Cell(region=firstwall_region)
firstwall_cell.fill = firstwall_material
firstwall_cell.name = 'firstwall'
additional_thickness = 0
all_layers_materials = [firstwall_material]
all_cells = [inner_void_cell, firstwall_cell]
for i, (layer_thickness, layer_enrichment, layer_breeder_fraction,
layer_multiplier_fraction) in enumerate(
zip(layer_thickness_fractions, layer_li6_enrichments,
layer_breeder_fractions, layer_multiplier_fractions)):
print(i, layer_thickness, layer_enrichment, layer_breeder_fraction)
layer_material = MultiMaterial(
'layer_' + str(i) + '_material',
materials=[
Material(blanket_breeder_material,
enrichment_fraction=layer_enrichment),
Material(blanket_multiplier_material),
Material(blanket_structural_material)
],
volume_fractions=[
layer_breeder_fraction, layer_multiplier_fraction,
blanket_structural_fraction
])
all_layers_materials.append(layer_material)
additional_thickness = additional_thickness + (
layer_thickness * thickness_fraction_scaler)
print('additional_thickness', additional_thickness)
if i == number_of_layers - 1:
layer_outer_surface = openmc.Sphere(r=inner_radius +
firstwall_thickness +
additional_thickness,
boundary_type='vacuum')
else:
layer_outer_surface = openmc.Sphere(r=inner_radius +
firstwall_thickness +
additional_thickness)
layer_inner_surface = surfaces[-1]
layer_region = -layer_outer_surface & +layer_inner_surface
layer_cell = openmc.Cell(region=layer_region)
layer_cell.fill = layer_material
layer_cell.name = 'layer_' + str(i) + '_cell'
surfaces.append(layer_outer_surface)
all_cells.append(layer_cell)
universe = openmc.Universe(cells=all_cells)
geom = openmc.Geometry(universe)
mats = openmc.Materials(all_layers_materials)
sett = openmc.Settings()
# batches = 3 # this is parsed as an argument
sett.batches = batches
sett.inactive = 10
sett.particles = 500
sett.run_mode = 'fixed source'
source = openmc.Source()
source.space = openmc.stats.Point((0, 0, 0))
source.angle = openmc.stats.Isotropic()
source.energy = openmc.stats.Muir(
e0=14080000.0, m_rat=5.0, kt=20000.0
) #neutron energy = 14.08MeV, AMU for D + T = 5, temperature is 20KeV
sett.source = source
#TALLIES#
tallies = openmc.Tallies()
# define filters
# cell_filter_breeder = openmc.CellFilter(breeder_blanket_cell)
particle_filter = openmc.ParticleFilter(['neutron'
]) #1 is neutron, 2 is photon
tally = openmc.Tally(name='TBR')
tally.filters = [particle_filter]
tally.scores = ['(n,Xt)'] #could be (n,Xt)
tallies.append(tally)
model = openmc.model.Model(geom, mats, sett, tallies)
model.export_to_xml()
# model.run()
openmc.lib.run()
sp = openmc.StatePoint('statepoint.' + str(batches) + '.h5')
tally = sp.get_tally(name='TBR')
df = tally.get_pandas_dataframe()
return df['mean'].sum()
def sphere_with_firstwall_model(
material_for_structure,
blanket_breeder_material,
blanket_coolant_material,
firstwall_coolant_material,
blanket_breeder_li6_enrichment, # this is a percentage
coolant_pressure, # this is in Pa
blanket_coolant_temperature_in_C,
firstwall_coolant_temperature_in_C,
blanket_breeder_fraction,
blanket_coolant_fraction,
blanket_structural_fraction,
blanket_breeder_temperature_in_C = None, #needed for liquid breeders like lithium lead
firstwall_thickness = 2.7, # this is in cm
blanket_thickness = 200, # this is in cm
inner_radius = 1000,
firstwall_armour_fraction = 0.106305, # equivilent to 3mm and based on https://doi.org/10.1016/j.fusengdes.2017.02.008
firstwall_coolant_fraction= 0.333507, # based on https://doi.org/10.1016/j.fusengdes.2017.02.008
firstwall_structural_fraction = 0.560188, # based on https://doi.org/10.1016/j.fusengdes.2017.02.008
blanket_multipler_material = None, #used for combined breeder multiplier options
blanket_multiplier_fraction = None, #used for combined breeder multiplier options
blanket_breeder_material_packing_fraction = None, #used for combined breeder multiplier options
blanket_multiplier_packing_fraction = None, #used for combined breeder multiplier options
blanket_multiplier_material = None #used for combined breeder multiplier options
):
breeder_percent_in_breeder_plus_multiplier_ratio = 100 * (blanket_breeder_fraction / (blanket_breeder_fraction + blanket_multiplier_fraction))
inputs = locals()
"""
This function builds materials for the homogenised blanket material, homogenised firstwall material
The creates a simple sphere geometry with a simple point source and TBR tally on the blanket
The function also carries out the simulation and writes the results to a JSON file
"""
# creates homogensied blanket material using a single breeder / multiplier material (e.g lithium lead)
if blanket_breeder_material == 'Pb842Li158':
blanket_material = MultiMaterial(material_tag = 'blanket_material',
materials = [
Material(material_name = material_for_structure),
Material(material_name = blanket_coolant_material,
temperature_in_C = blanket_coolant_temperature_in_C,
pressure_in_Pa = coolant_pressure),
Material(material_name = blanket_breeder_material,
enrichment = blanket_breeder_li6_enrichment,
temperature_in_C = blanket_breeder_temperature_in_C),
],
fracs = [blanket_structural_fraction,
blanket_coolant_fraction,
blanket_breeder_fraction],
percent_type='vo'
).openmc_material
# creates homogensied blanket material using a combined breeder multiplier material (e.g lithium ceramic with be multiplier)
else:
blanket_material = MultiMaterial(
material_tag = 'blanket_material',
materials = [
Material(material_name = material_for_structure),
Material(material_name = blanket_coolant_material,
temperature_in_C = blanket_coolant_temperature_in_C,
pressure_in_Pa = coolant_pressure),
Material(material_name = blanket_breeder_material,
enrichment = blanket_breeder_li6_enrichment,
packing_fraction = blanket_breeder_material_packing_fraction),
Material(material_name = blanket_multipler_material,
packing_fraction = blanket_multiplier_packing_fraction),
],
fracs = [blanket_structural_fraction,
blanket_coolant_fraction,
blanket_breeder_fraction,
blanket_multiplier_fraction],
percent_type='vo'
).openmc_material
# creates homogensied firstwall material with eurofer, tungsten and a coolant
firstwall_material = MultiMaterial(material_tag = 'firstwall_material',
materials = [
Material(material_name = 'tungsten'),
Material(material_name = firstwall_coolant_material,
temperature_in_C = firstwall_coolant_temperature_in_C,
pressure_in_Pa = coolant_pressure),
Material(material_name = 'eurofer')],
fracs = [firstwall_armour_fraction,
firstwall_coolant_fraction,
firstwall_structural_fraction]
).openmc_material
mats = openmc.Materials([blanket_material, firstwall_material])
# creates surfaces
breeder_blanket_inner_surface = openmc.Sphere(r=inner_radius+firstwall_thickness)
firstwall_outer_surface = openmc.Sphere(r=inner_radius)
inner_void_region = -firstwall_outer_surface
inner_void_cell = openmc.Cell(region=inner_void_region)
inner_void_cell.name = 'inner_void'
firstwall_region = +firstwall_outer_surface & -breeder_blanket_inner_surface
firstwall_cell = openmc.Cell(name='firstwall', region=firstwall_region)
firstwall_cell.fill = firstwall_material
breeder_blanket_outer_surface = openmc.Sphere(r=inner_radius+firstwall_thickness+blanket_thickness, boundary_type='vacuum')
breeder_blanket_region = -breeder_blanket_outer_surface & +breeder_blanket_inner_surface
breeder_blanket_cell = openmc.Cell(name = 'breeder_blanket', region=breeder_blanket_region)
breeder_blanket_cell.fill = blanket_material
universe = openmc.Universe(cells=[inner_void_cell,
firstwall_cell,
breeder_blanket_cell])
geom = openmc.Geometry(universe)
# assigns simulation settings
sett = openmc.Settings()
sett.batches = 200 # this is minimum number of batches that will be run
sett.trigger_active = True
sett.trigger_max_batches = 1500 # this is maximum number of batches that will be run
sett.particles = 300
sett.verbosity = 1
sett.run_mode = 'fixed source'
# sets a 14MeV (distributuion) point source
source = openmc.Source()
source.space = openmc.stats.Point((0,0,0))
source.angle = openmc.stats.Isotropic()
source.energy = openmc.stats.Muir(e0=14080000.0, m_rat=5.0, kt=20000.0) #neutron energy = 14.08MeV, AMU for D + T = 5, temperature is 20KeV
sett.source = source
# this is the tally set up
tallies = openmc.Tallies()
# define filters
cell_filter_breeder = openmc.CellFilter(breeder_blanket_cell)
particle_filter = openmc.ParticleFilter(['neutron'])
# creates the TBR tally using the filters and sets a completion trigger
tally = openmc.Tally(name='TBR')
tally.filters = [cell_filter_breeder, particle_filter]
tally.scores = ['(n,Xt)'] # where X is a wildcard, if MT 105 or (n,t) then some tritium production will be missed, for example (n,nt) which happens in Li7 would be missed
tally.triggers = [openmc.Trigger(trigger_type='rel_err', threshold=0.0001)] # This stops the simulation if the threshold is meet
tallies.append(tally)
# collects all the model parts and runs the model
model = openmc.model.Model(geom, mats, sett, tallies)
sp_filename = model.run(output=False)
# opens the output file and retrieves the tally results
sp = openmc.StatePoint(sp_filename)
tally = sp.get_tally(name='TBR')
df = tally.get_pandas_dataframe()
tally_result = df['mean'].sum()
tally_std_dev = df['std. dev.'].sum()
# combines the tally results with the input data
inputs.update({'tbr': tally_result})
inputs.update({'tbr_error': tally_std_dev})
return inputs
]:
if float_key in material.keys():
material[float_key] = float(material[float_key])
if len(materials) == 1:
for material in breeder_materials:
breeder_material = Material(**material).neutronics_material
else:
multimaterials = []
volume_fractions = []
for material in breeder_materials:
multimaterials.append(Material(**material))
volume_fractions.append(material['volume_fraction'])
breeder_material = MultiMaterial(
material_name='breeder_material',
materials=multimaterials,
volume_fractions=volume_fractions).neutronics_material
if model == 'sphere with firstwall':
for material in firstwall_materials:
for float_key in [
'enrichment_fraction', 'packing_fraction',
'volume_fraction', 'temperature_in_C'
]:
if float_key in material.keys():
material[float_key] = float(material[float_key])
if len(firstwall_materials) == 1:
for material in firstwall_materials:
firstwall_material = Material(**material).neutronics_material
else: