def incorrect_simulation_batches_to_small():
"""Sets simulation batch below 2 which should raise an error"""
paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'eurofer'},
simulation_batches=1)
def incorrect_merge_tolerance_too_small():
"""Set merge_tolerance as a negative number which should raise an error"""
paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'eurofer'},
merge_tolerance=-3)
def incorrect_simulation_particles_per_batch_wrong_type():
"""Sets simulation_particles_per_batch below 2 which should raise an error"""
paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'eurofer'},
simulation_particles_per_batch='one')
def incorrect_merge_tolerance():
"""Set merge_tolerance as a string which should raise an error"""
paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'eurofer'},
merge_tolerance='coucou')
def test_neutronics_component_3d_and_2d_mesh_simulation(self):
"""Makes a neutronics model and simulates with a 3D and 2D mesh tally
and checks that the vtk and png files are produced. This checks the
mesh ID values don't overlap"""
os.system('rm *.h5')
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'Be'},
mesh_tally_3d=['heating'],
mesh_tally_2d=['heating'],
simulation_batches=2,
simulation_particles_per_batch=2
)
# performs an openmc simulation on the model
output_filename = my_model.simulate(method='pymoab')
results = openmc.StatePoint(output_filename)
assert len(results.meshes) == 4 # one 3D and three 2D
assert len(results.tallies.items()) == 4 # one 3D and three 2D
assert Path(output_filename).exists() is True
assert Path('heating_on_3D_mesh.vtk').exists() is True
assert Path("heating_on_2D_mesh_xz.png").exists() is True
assert Path("heating_on_2D_mesh_xy.png").exists() is True
assert Path("heating_on_2D_mesh_yz.png").exists() is True
def test_neutronics_component_2d_mesh_simulation(self):
"""Makes a neutronics model and simulates with a 2D mesh tally"""
os.system('rm *_on_2D_mesh_*.png')
os.system('rm *.h5')
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'Be'},
mesh_tally_2d=['heating'],
simulation_batches=2,
simulation_particles_per_batch=2
)
# performs an openmc simulation on the model
output_filename = my_model.simulate(method='pymoab')
results = openmc.StatePoint(output_filename)
assert len(results.meshes) == 3
assert len(results.tallies.items()) == 3
assert Path("heating_on_2D_mesh_xz.png").exists() is True
assert Path("heating_on_2D_mesh_xy.png").exists() is True
assert Path("heating_on_2D_mesh_yz.png").exists() is True
def test_cell_tally_output_file_creation(self):
"""Performs a neutronics simulation and checks the cell tally output
file is created and named correctly"""
os.system('rm custom_name.json')
os.system('rm results.json')
test_mat = openmc.Material()
test_mat.add_element('Fe', 1.0)
test_mat.set_density(units='g/cm3', density=4.2)
# converts the geometry into a neutronics geometry
# this simulation has no tally to test this edge case
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': test_mat},
simulation_batches=2,
simulation_particles_per_batch=2
)
# performs an openmc simulation on the model
output_filename = my_model.simulate(
method='pymoab',
cell_tally_results_filename='custom_name.json'
)
assert output_filename.name == 'statepoint.2.h5'
assert Path('custom_name.json').exists() is True
output_filename = my_model.simulate(
method='pymoab',
)
assert Path('results.json').exists() is True
def main():
my_shape = paramak.CenterColumnShieldHyperbola(
height=500,
inner_radius=50,
mid_radius=60,
outer_radius=100,
material_tag='center_column_shield_mat')
# makes the openmc neutron source at x,y,z 0, 0, 0 with isotropic
# directions
source = openmc.Source()
source.space = openmc.stats.Point((0, 0, 0))
source.energy = openmc.stats.Discrete([14e6], [1])
source.angle = openmc.stats.Isotropic()
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=my_shape,
source=source,
materials={'center_column_shield_mat': 'Be'},
cell_tallies=['(n,Xa)', '(n,Xt)', '(n,Xp)'],
mesh_tally_3d=['(n,Xa)', '(n,Xt)', '(n,Xp)'],
mesh_tally_2d=['(n,Xa)', '(n,Xt)', '(n,Xp)'],
simulation_batches=10,
simulation_particles_per_batch=200)
# performs an openmc simulation on the model
my_model.simulate(method='pymoab')
# this extracts the values from the results dictionary
print(my_model.results)
def incorrect_materials():
"""Set a material as a string which should raise an error"""
paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials='coucou',
)
def test_neutronics_component_simulation_with_openmc_mat(self):
"""Makes a neutronics model and simulates with a cell tally"""
test_mat = openmc.Material()
test_mat.add_element('Fe', 1.0)
test_mat.set_density(units='g/cm3', density=4.2)
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': test_mat},
cell_tallies=['heating'],
simulation_batches=2,
simulation_particles_per_batch=2
)
# performs an openmc simulation on the model
output_filename = my_model.simulate(
method='pymoab',
)
assert output_filename.name == 'statepoint.2.h5'
results = openmc.StatePoint(output_filename)
assert len(results.tallies.items()) == 1
# extracts the heat from the results dictionary
heat = my_model.results['center_column_shield_mat_heating']['Watts']['result']
assert heat > 0
def test_neutronics_component_3d_mesh_simulation(self):
"""Makes a neutronics model and simulates with a 3D mesh tally and
checks that the vtk file is produced"""
os.system('rm *.h5')
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'Be'},
mesh_tally_3d=['heating', '(n,Xt)'],
simulation_batches=2,
simulation_particles_per_batch=2
)
# performs an openmc simulation on the model
output_filename = my_model.simulate(method='pymoab')
results = openmc.StatePoint(output_filename)
assert len(results.meshes) == 1
assert len(results.tallies.items()) == 2
assert Path(output_filename).exists() is True
assert Path('heating_on_3D_mesh.vtk').exists() is True
assert Path('n-Xt_on_3D_mesh.vtk').exists() is True
def test_reactor_from_shapes_cell_tallies(self):
"""Makes a reactor from two shapes, then mades a neutronics model
and tests the TBR simulation value"""
test_shape = paramak.RotateStraightShape(
points=[(0, 0), (0, 20), (20, 20)],
material_tag='mat1',
)
test_shape2 = paramak.RotateSplineShape(
points=[(100, 100), (100, -100), (200, -100), (200, 100)],
material_tag='blanket_mat',
rotation_angle=180
)
test_reactor = paramak.Reactor([test_shape, test_shape2])
neutronics_model = paramak.NeutronicsModel(
geometry=test_reactor,
source=self.source,
materials={
'mat1': 'copper',
'blanket_mat': 'FLiNaK', # used as O18 is not in nndc nuc data
},
cell_tallies=['TBR', 'heating', 'flux'],
simulation_batches=2,
simulation_particles_per_batch=10,
)
# starts the neutronics simulation using trelis
neutronics_model.simulate(verbose=False, method='pymoab')
def incorrect_mesh_tally_3d_type():
"""Set a mesh_tally_3d that is the wrong type which should raise an error"""
paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'eurofer'},
mesh_tally_3d=1,
)
def incorrect_mesh_tally_3d():
"""Set a mesh_tally_3d that is not accepted which should raise an error"""
paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'eurofer'},
mesh_tally_3d=['coucou'],
)
def incorrect_materials_type():
"""Sets a material as an int which should raise an error"""
test_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 23},
)
test_model.create_materials()
def missing_dagmc_not_watertight_file():
"""Sets faceting_tolerance as a string which should raise an error"""
test_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'eurofer'},
)
test_model._make_watertight()
def make_model_and_simulate(temperature):
"""Makes a neutronics Reactor model and simulates the flux"""
# makes the 3d geometry from input parameters
my_reactor = paramak.SubmersionTokamak(
inner_bore_radial_thickness=30,
inboard_tf_leg_radial_thickness=30,
center_column_shield_radial_thickness=30,
divertor_radial_thickness=80,
inner_plasma_gap_radial_thickness=50,
plasma_radial_thickness=200,
outer_plasma_gap_radial_thickness=50,
firstwall_radial_thickness=30,
blanket_rear_wall_radial_thickness=30,
rotation_angle=180,
support_radial_thickness=50,
inboard_blanket_radial_thickness=30,
outboard_blanket_radial_thickness=30,
elongation=2.75,
triangularity=0.5,
)
# this can just be set as a string as temperature is needed for this
# material
flibe = nmm.Material('FLiBe', temperature_in_C=temperature)
source = openmc.Source()
# sets the location of the source to x=0 y=0 z=0
source.space = openmc.stats.Point((my_reactor.major_radius, 0, 0))
# sets the direction to isotropic
source.angle = openmc.stats.Isotropic()
# sets the energy distribution to 100% 14MeV neutrons
source.energy = openmc.stats.Discrete([14e6], [1])
# makes the neutronics model from the geometry and material allocations
neutronics_model = paramak.NeutronicsModel(
geometry=my_reactor,
source=source,
materials={
'inboard_tf_coils_mat': 'eurofer',
'center_column_shield_mat': 'eurofer',
'divertor_mat': 'eurofer',
'firstwall_mat': 'eurofer',
'blanket_rear_wall_mat': 'eurofer',
'blanket_mat': flibe,
'supports_mat': 'eurofer'
},
cell_tallies=['TBR'],
simulation_batches=5,
simulation_particles_per_batch=1e4,
faceting_tolerance=1e-4,
merge_tolerance=1e-4)
# simulate the neutronics model
neutronics_model.simulate(method='trelis')
return neutronics_model.results['TBR']
def make_model_and_simulate():
simulation_values = []
for mid_radius in [60, 70, 80]:
# makes the component with a few different size mid radius values
my_shape = paramak.CenterColumnShieldHyperbola(
height=500,
inner_radius=50,
mid_radius=mid_radius,
outer_radius=100,
material_tag='center_column_shield_mat'
)
my_shape.export_stp('my_shape' + str(mid_radius) + '.stp')
# makes the openmc neutron source at x,y,z 0, 0, 0 with isotropic
# diections
source = openmc.Source()
source.space = openmc.stats.Point((0, 0, 0))
source.angle = openmc.stats.Isotropic()
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=my_shape,
source=source,
materials={'center_column_shield_mat': 'eurofer'},
cell_tallies=['heating', 'TBR'],
mesh_tally_2d=['heating'],
mesh_tally_3d=['heating'],
simulation_batches=10, # should be increased for more accurate result
simulation_particles_per_batch=10 # settings are low to reduce time required
)
# performs an openmc simulation on the model
my_model.simulate(method='pymoab')
# extracts the heat from the results dictionary
heat = my_model.results['center_column_shield_mat_heating']['Watts']['result']
# adds the heat and the mid radius value to a list
simulation_values.append((mid_radius, heat))
# plots the simualtion results vs the mid_radius used for the simulation
plt.plot(
[i[0] for i in simulation_values],
[i[1] for i in simulation_values],
'-p'
)
# adds labels to the graph
plt.title("heating vs thickness")
plt.xlabel("thickness (cm)")
plt.ylabel("heating (watts)")
plt.savefig('heating_vs_thickness.svg')
plt.show()
def test_merge_tolerance_setting_and_getting(self):
"""Makes a neutronics model and checks the default merge_tolerance"""
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'eurofer'},
)
assert my_model.merge_tolerance == 1e-4
my_model.merge_tolerance = 1e-6
assert my_model.merge_tolerance == 1e-6
def test_neutronics_component_cell_simulation_heating(self):
"""Makes a neutronics model and simulates with a cell tally"""
os.system('rm *.h5')
mat = openmc.Material()
mat.add_element('Li', 1)
mat.set_density('g/cm3', 2.1)
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': mat},
cell_tallies=['heating', 'flux', 'TBR', 'spectra'],
simulation_batches=2,
simulation_particles_per_batch=2)
# performs an openmc simulation on the model
output_filename = my_model.simulate(method='pymoab')
results = openmc.StatePoint(output_filename)
# spectra add two tallies in this case (photons and neutrons)
# TBR adds two tallies global TBR and material TBR
assert len(results.tallies.items()) == 6
assert len(results.meshes) == 0
# extracts the heat from the results dictionary
heat = my_model.results['center_column_shield_mat_heating']['Watts'][
'result']
flux = my_model.results['center_column_shield_mat_flux'][
'Flux per source particle']['result']
mat_tbr = my_model.results['center_column_shield_mat_TBR']['result']
tbr = my_model.results['TBR']['result']
spectra_neutrons = my_model.results[
'center_column_shield_mat_neutron_spectra'][
'Flux per source particle']['result']
spectra_photons = my_model.results[
'center_column_shield_mat_photon_spectra'][
'Flux per source particle']['result']
energy = my_model.results['center_column_shield_mat_photon_spectra'][
'Flux per source particle']['energy']
assert heat > 0
assert flux > 0
assert tbr > 0
assert mat_tbr > 0
assert mat_tbr == tbr # as there is just one shape
assert len(energy) == 710
assert len(spectra_neutrons) == 709
assert len(spectra_photons) == 709
def simulate_cylinder_cask_cad(self, material, source, height,
outer_radius, thickness, batches,
particles):
"""Makes a CAD cask geometry runs a simulation and returns the result"""
top_cap_cell = paramak.RotateStraightShape(
stp_filename='top_cap_cell.stp',
material_tag='test_mat',
points=[
(outer_radius, height * 0.5),
(outer_radius, (height * 0.5) + thickness),
(0, (height * 0.5) + thickness),
(0, height * 0.5),
],
)
bottom_cap_cell = paramak.RotateStraightShape(
stp_filename='bottom_cap_cell.stp',
material_tag='test_mat',
points=[
(outer_radius, -height * 0.5),
(outer_radius, (-height * 0.5) - thickness),
(0, (-height * 0.5) - thickness),
(0, -height * 0.5),
])
cylinder_cell = paramak.CenterColumnShieldCylinder(
height=height,
inner_radius=outer_radius - thickness,
outer_radius=outer_radius,
material_tag='test_mat',
)
my_geometry = paramak.Reactor(
[cylinder_cell, bottom_cap_cell, top_cap_cell])
my_model = paramak.NeutronicsModel(
geometry=my_geometry,
source=source,
simulation_batches=batches,
simulation_particles_per_batch=particles,
materials={'test_mat': material},
cell_tallies=['heating'])
my_model.simulate(method='pymoab')
# scaled from MeV to eV
return my_model.results['test_mat_heating']['MeV per source particle'][
'result'] * 1e6
def make_model_and_simulate():
"""Makes a neutronics Reactor model and simulates the heat deposition"""
# makes the 3d geometry
my_reactor = paramak.CenterColumnStudyReactor(
inner_bore_radial_thickness=20,
inboard_tf_leg_radial_thickness=50,
center_column_shield_radial_thickness_mid=50,
center_column_shield_radial_thickness_upper=100,
inboard_firstwall_radial_thickness=20,
divertor_radial_thickness=100,
inner_plasma_gap_radial_thickness=80,
plasma_radial_thickness=200,
outer_plasma_gap_radial_thickness=90,
elongation=2.75,
triangularity=0.5,
plasma_gap_vertical_thickness=40,
center_column_arc_vertical_thickness=520,
rotation_angle=360)
source = openmc.Source()
# sets the location of the source to x=0 y=0 z=0
source.space = openmc.stats.Point((my_reactor.major_radius, 0, 0))
# sets the direction to isotropic
source.angle = openmc.stats.Isotropic()
# sets the energy distribution to 100% 14MeV neutrons
source.energy = openmc.stats.Discrete([14e6], [1])
# creates a neutronics model from the geometry and assigned materials
neutronics_model = paramak.NeutronicsModel(
geometry=my_reactor,
source=source,
materials={
'inboard_tf_coils_mat': 'eurofer',
'center_column_shield_mat': 'eurofer',
'divertor_mat': 'eurofer',
'firstwall_mat': 'eurofer',
'blanket_mat': 'Li4SiO4'
},
cell_tallies=['heating'],
simulation_batches=5,
simulation_particles_per_batch=1e4,
)
# starts the neutronics simulation
neutronics_model.simulate(method='trelis')
# prints the results
print(neutronics_model.results)
def simulation_with_previous_h5m_file(self):
"""This performs a simulation using previously created h5m file"""
os.system('rm *.h5m')
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'WC'},
)
my_model.create_neutronics_geometry(method='pymoab')
my_model.simulate(method=None)
my_model.results is not None
def test_batches_and_particles_convert_to_int(self):
"""Makes a neutronics model and simulates with a 3D and 2D mesh tally
and checks that the vtk and png files are produced. This checks the
mesh ID values don't overlap"""
os.system('rm *.h5')
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': 'Be'},
simulation_batches=3.1,
simulation_particles_per_batch=2.1)
assert isinstance(my_model.simulation_batches, int)
assert my_model.simulation_batches == 3
assert isinstance(my_model.simulation_particles_per_batch, int)
assert my_model.simulation_particles_per_batch == 2
def test_reactor_from_shapes_2d_mesh_tallies(self):
"""Makes a reactor from two shapes, then mades a neutronics model
and tests the TBR simulation value"""
os.system('rm *_on_2D_mesh_*.png')
test_shape = paramak.RotateStraightShape(
points=[(0, 0), (0, 20), (20, 20)],
material_tag='mat1',
)
test_shape2 = paramak.RotateSplineShape(
points=[(100, 100), (100, -100), (200, -100), (200, 100)],
material_tag='blanket_mat',
rotation_angle=180
)
test_reactor = paramak.Reactor([test_shape, test_shape2])
neutronics_model = paramak.NeutronicsModel(
geometry=test_reactor,
source=self.source,
materials={
'mat1': 'copper',
'blanket_mat': 'FLiNaK', # used as O18 is not in nndc nuc data
},
mesh_tally_2d=['(n,Xt)', 'heating', 'flux'],
simulation_batches=2,
simulation_particles_per_batch=10,
)
# starts the neutronics simulation using trelis
neutronics_model.simulate(verbose=False, method='pymoab')
assert Path("n-Xt_on_2D_mesh_xz.png").exists() is True
assert Path("n-Xt_on_2D_mesh_xy.png").exists() is True
assert Path("n-Xt_on_2D_mesh_yz.png").exists() is True
assert Path("heating_on_2D_mesh_xz.png").exists() is True
assert Path("heating_on_2D_mesh_xy.png").exists() is True
assert Path("heating_on_2D_mesh_yz.png").exists() is True
assert Path("flux_on_2D_mesh_xz.png").exists() is True
assert Path("flux_on_2D_mesh_xy.png").exists() is True
assert Path("flux_on_2D_mesh_yz.png").exists() is True
def test_incorrect_method():
"""Makes a BallReactor neutronics model and simulates the TBR"""
# makes the neutronics material
neutronics_model = paramak.NeutronicsModel(
geometry=self.my_reactor,
source=self.source,
materials={
'inboard_tf_coils_mat': 'copper',
'center_column_shield_mat': 'WC',
'divertor_mat': 'eurofer',
'firstwall_mat': 'eurofer',
'blanket_mat': 'FLiNaK', # used as O18 is not in nndc nuc data
'blanket_rear_wall_mat': 'eurofer'},
cell_tallies=['TBR', 'flux', 'heating'],
simulation_batches=42,
simulation_particles_per_batch=84,
)
neutronics_model.create_neutronics_geometry(method='incorrect')
def test_neutronics_model_attributes(self):
"""Makes a BallReactor neutronics model and simulates the TBR"""
# makes the neutronics material
neutronics_model = paramak.NeutronicsModel(
geometry=self.my_reactor,
source=openmc.Source(),
materials={
'inboard_tf_coils_mat': 'copper',
'center_column_shield_mat': 'WC',
'divertor_mat': 'eurofer',
'firstwall_mat': 'eurofer',
'blanket_mat':
self.blanket_material, # use of homogenised material
'blanket_rear_wall_mat': 'eurofer'
},
cell_tallies=['TBR', 'flux', 'heating'],
simulation_batches=42,
simulation_particles_per_batch=84,
)
assert neutronics_model.geometry == self.my_reactor
assert neutronics_model.materials == {
'inboard_tf_coils_mat': 'copper',
'center_column_shield_mat': 'WC',
'divertor_mat': 'eurofer',
'firstwall_mat': 'eurofer',
'blanket_mat': self.blanket_material,
'blanket_rear_wall_mat': 'eurofer'
}
assert neutronics_model.cell_tallies == ['TBR', 'flux', 'heating']
assert neutronics_model.simulation_batches == 42
assert isinstance(neutronics_model.simulation_batches, int)
assert neutronics_model.simulation_particles_per_batch == 84
assert isinstance(neutronics_model.simulation_particles_per_batch, int)
def test_neutronics_component_simulation_with_nmm(self):
"""Makes a neutronics model and simulates with a cell tally"""
test_mat = nmm.Material('Be')
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=self.my_shape,
source=self.source,
materials={'center_column_shield_mat': test_mat},
cell_tallies=['heating'],
simulation_batches=2,
simulation_particles_per_batch=2
)
# performs an openmc simulation on the model
output_filename = my_model.simulate(method='pymoab')
results = openmc.StatePoint(output_filename)
assert len(results.tallies.items()) == 1
# extracts the heat from the results dictionary
heat = my_model.results['center_column_shield_mat_heating']['Watts']['result']
assert heat > 0
def make_model_and_simulate():
"""Makes a neutronics Reactor model and simulates the TBR with specified materials"""
# based on
# http://www.euro-fusionscipub.org/wp-content/uploads/WPBBCP16_15535_submitted.pdf
firstwall_radial_thickness = 3.0
firstwall_armour_material = "tungsten"
firstwall_coolant_material = "He"
firstwall_structural_material = "eurofer"
firstwall_armour_fraction = 0.106305
firstwall_coolant_fraction = 0.333507
firstwall_coolant_temperature_C = 400
firstwall_coolant_pressure_Pa = 8e6
firstwall_structural_fraction = 0.560188
firstwall_material = nmm.MultiMaterial(
material_tag="firstwall_mat",
materials=[
nmm.Material(
material_name=firstwall_coolant_material,
temperature_in_C=firstwall_coolant_temperature_C,
pressure_in_Pa=firstwall_coolant_pressure_Pa,
),
nmm.Material(material_name=firstwall_structural_material),
nmm.Material(material_name=firstwall_armour_material),
],
fracs=[
firstwall_coolant_fraction,
firstwall_structural_fraction,
firstwall_armour_fraction,
],
percent_type="vo")
# based on
# https://www.sciencedirect.com/science/article/pii/S2352179118300437
blanket_rear_wall_coolant_material = "H2O"
blanket_rear_wall_structural_material = "eurofer"
blanket_rear_wall_coolant_fraction = 0.3
blanket_rear_wall_structural_fraction = 0.7
blanket_rear_wall_coolant_temperature_C = 200
blanket_rear_wall_coolant_pressure_Pa = 1e6
blanket_rear_wall_material = nmm.MultiMaterial(
material_tag="blanket_rear_wall_mat",
materials=[
nmm.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,
),
nmm.Material(material_name=blanket_rear_wall_structural_material),
],
fracs=[
blanket_rear_wall_coolant_fraction,
blanket_rear_wall_structural_fraction,
],
percent_type="vo")
# based on
# https://www.sciencedirect.com/science/article/pii/S2352179118300437
blanket_lithium6_enrichment_percent = 60
blanket_breeder_material = "Li4SiO4"
blanket_coolant_material = "He"
blanket_multiplier_material = "Be"
blanket_structural_material = "eurofer"
blanket_breeder_fraction = 0.15
blanket_coolant_fraction = 0.05
blanket_multiplier_fraction = 0.6
blanket_structural_fraction = 0.2
blanket_breeder_packing_fraction = 0.64
blanket_multiplier_packing_fraction = 0.64
blanket_coolant_temperature_C = 500
blanket_coolant_pressure_Pa = 1e6
blanket_breeder_temperature_C = 600
blanket_breeder_pressure_Pa = 8e6
blanket_material = nmm.MultiMaterial(
material_tag="blanket_mat",
materials=[
nmm.Material(
material_name=blanket_coolant_material,
temperature_in_C=blanket_coolant_temperature_C,
pressure_in_Pa=blanket_coolant_pressure_Pa,
),
nmm.Material(material_name=blanket_structural_material),
nmm.Material(
material_name=blanket_multiplier_material,
packing_fraction=blanket_multiplier_packing_fraction,
),
nmm.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")
# based on
# https://www.sciencedirect.com/science/article/pii/S2352179118300437
divertor_coolant_fraction = 0.57195798876
divertor_structural_fraction = 0.42804201123
divertor_coolant_material = "H2O"
divertor_structural_material = "tungsten"
divertor_coolant_temperature_C = 150
divertor_coolant_pressure_Pa = 5e6
divertor_material = nmm.MultiMaterial(
material_tag="divertor_mat",
materials=[
nmm.Material(
material_name=divertor_coolant_material,
temperature_in_C=divertor_coolant_temperature_C,
pressure_in_Pa=divertor_coolant_pressure_Pa,
),
nmm.Material(material_name=divertor_structural_material),
],
fracs=[divertor_coolant_fraction, divertor_structural_fraction],
percent_type="vo")
# based on
# https://pdfs.semanticscholar.org/95fa/4dae7d82af89adf711b97e75a241051c7129.pdf
center_column_shield_coolant_fraction = 0.13
center_column_shield_structural_fraction = 0.57
center_column_shield_coolant_material = "H2O"
center_column_shield_structural_material = "tungsten"
center_column_shield_coolant_temperature_C = 150
center_column_shield_coolant_pressure_Pa = 5e6
center_column_shield_material = nmm.MultiMaterial(
material_tag="center_column_shield_mat",
materials=[
nmm.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,
),
nmm.Material(
material_name=center_column_shield_structural_material),
],
fracs=[
center_column_shield_coolant_fraction,
center_column_shield_structural_fraction,
],
percent_type="vo")
# based on
# https://pdfs.semanticscholar.org/95fa/4dae7d82af89adf711b97e75a241051c7129.pdf
inboard_tf_coils_conductor_fraction = 0.57
inboard_tf_coils_coolant_fraction = 0.05
inboard_tf_coils_structure_fraction = 0.38
inboard_tf_coils_conductor_material = "copper"
inboard_tf_coils_coolant_material = "He"
inboard_tf_coils_structure_material = "SS_316L_N_IG"
inboard_tf_coils_coolant_temperature_C = 30
inboard_tf_coils_coolant_pressure_Pa = 8e6
inboard_tf_coils_material = nmm.MultiMaterial(
material_tag="inboard_tf_coils_mat",
materials=[
nmm.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,
),
nmm.Material(material_name=inboard_tf_coils_conductor_material),
nmm.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")
# makes the 3d geometry
my_reactor = paramak.BallReactor(
inner_bore_radial_thickness=1,
inboard_tf_leg_radial_thickness=30,
center_column_shield_radial_thickness=60,
divertor_radial_thickness=50,
inner_plasma_gap_radial_thickness=30,
plasma_radial_thickness=300,
outer_plasma_gap_radial_thickness=30,
firstwall_radial_thickness=firstwall_radial_thickness,
# http://www.euro-fusionscipub.org/wp-content/uploads/WPBBCP16_15535_submitted.pdf
blanket_radial_thickness=100,
blanket_rear_wall_radial_thickness=3,
elongation=2.75,
triangularity=0.5,
number_of_tf_coils=16,
rotation_angle=360,
)
source = openmc.Source()
# sets the location of the source to x=0 y=0 z=0
source.space = openmc.stats.Point((my_reactor.major_radius, 0, 0))
# sets the direction to isotropic
source.angle = openmc.stats.Isotropic()
# sets the energy distribution to 100% 14MeV neutrons
source.energy = openmc.stats.Discrete([14e6], [1])
# makes the neutronics material
neutronics_model = paramak.NeutronicsModel(
geometry=my_reactor,
source=source,
materials={
'inboard_tf_coils_mat': inboard_tf_coils_material,
'center_column_shield_mat': center_column_shield_material,
'divertor_mat': divertor_material,
'firstwall_mat': firstwall_material,
'blanket_mat': blanket_material,
'blanket_rear_wall_mat': blanket_rear_wall_material
},
cell_tallies=['TBR'],
simulation_batches=5,
simulation_particles_per_batch=1e4,
)
# starts the neutronics simulation
neutronics_model.simulate(method='trelis')
# prints the simulation results to screen
print('TBR', neutronics_model.results['TBR'])
inner_radius=50,
mid_radius=60,
outer_radius=100,
material_tag='center_column_shield_mat')
# makes the openmc neutron source at x,y,z 0, 0, 0 with isotropic directions
source = openmc.Source()
source.space = openmc.stats.Point((0, 0, 0))
source.energy = openmc.stats.Discrete([14e6], [1])
source.angle = openmc.stats.Isotropic()
# converts the geometry into a neutronics geometry
my_model = paramak.NeutronicsModel(
geometry=my_shape,
source=source,
materials={'center_column_shield_mat': 'Be'},
cell_tallies=['heating', 'flux', 'TBR', 'spectra'],
simulation_batches=10,
simulation_particles_per_batch=200)
# performs an openmc simulation on the model
output_filename = my_model.simulate(method='pymoab')
# this extracts the values from the results dictionary
energy_bins = my_model.results['center_column_shield_mat_photon_spectra'][
'Flux per source particle']['energy']
neutron_spectra = my_model.results['center_column_shield_mat_neutron_spectra'][
'Flux per source particle']['result']
photon_spectra = my_model.results['center_column_shield_mat_photon_spectra'][
'Flux per source particle']['result']
