def _get_results(self,
num_iters=True,
keff=True,
fluxes=True,
num_fsrs=True,
num_tracks=True,
num_segments=True,
hash_output=True):
"""Digest info from the mesh tallies and return as a string."""
# Create OpenMOC Mesh on which to tally reaction rates
mesh = process.Mesh()
mesh.dimension = [4, 4]
mesh.lower_left = [-2., -2.]
mesh.upper_right = [2., 2.]
mesh.width = [1., 1.]
outstr = ""
for rxn in ('fission', 'flux', 'total', 'nu-fission', 'scatter'):
# Tally OpenMOC reaction rates on the Mesh
rxn_rates = mesh.tally_reaction_rates_on_mesh(self.solver,
rxn,
volume='integrated')
# Append reaction rates to the output string
outstr += rxn.title() + ' Rate Mesh Tally\n'
rates = ['{0:12.6E}'.format(rate) for rate in rxn_rates.ravel()]
outstr += '\n'.join(rates) + '\n'
return outstr
def _get_results(self, num_iters=True, keff=True, fluxes=True,
num_fsrs=True, num_tracks=True, num_segments=True,
hash_output=True):
"""Digest info from the mesh tallies and return as a string."""
# Create OpenMOC Mesh on which to tally fission rates
mesh = process.Mesh()
mesh.dimension = [4, 4]
mesh.lower_left = [-2., -2.]
mesh.upper_right = [2., 2.]
mesh.width = [1., 1.]
# Tally OpenMOC fission rates on the Mesh
fiss_rates = mesh.tally_fission_rates(self.solver)
# Append fission rates to the output string
outstr = 'Fission Rate Mesh Tally\n'
rates = ['{0:12.6E}'.format(rate) for rate in fiss_rates.ravel()]
outstr += '\n'.join(rates) + '\n'
# Retrieve the Materials and number of groups from the geometry
materials = self.input_set.geometry.getAllMaterials()
num_groups = self.input_set.geometry.getNumEnergyGroups()
# Aggregate the total cross sections for each Material
# into a dictionary to pass to the mesh tally
domains_to_coeffs = {}
for material_id in materials:
domains_to_coeffs[material_id] = np.zeros(num_groups)
for group in range(num_groups):
domains_to_coeffs[material_id][group] = \
materials[material_id].getSigmaTByGroup(group+1)
# Tally volume-averaged OpenMOC total rates on the Mesh
tot_rates = mesh.tally_on_mesh(self.solver, domains_to_coeffs,
domain_type='material',
volume='integrated')
# Append total rates to the output string
outstr += 'Total Rate Mesh Tally\n'
rates = ['{0:12.6E}'.format(rate) for rate in tot_rates.ravel()]
outstr += '\n'.join(rates) + '\n'
return outstr
def _get_results(self, num_iters=True, keff=True, fluxes=True,
num_fsrs=True, num_tracks=True, num_segments=True,
hash_output=True):
"""Digest info from the mesh tallies and return as a string."""
# Create OpenMOC Mesh on which to tally fission rates
mesh = process.Mesh()
mesh.dimension = [4, 4]
mesh.lower_left = [-2., -2.]
mesh.upper_right = [2., 2.]
mesh.width = [1., 1.]
# Tally OpenMOC fission rates on the Mesh
fiss_rates = mesh.tally_fission_rates(self.solver)
# Append fission rates to the output string
outstr = 'Fission Rate Mesh Tally\n'
rates = ['{0:12.6E}'.format(rate) for rate in fiss_rates.ravel()]
outstr += '\n'.join(rates) + '\n'
# Retrieve the Materials and number of groups from the geometry
materials = self.input_set.geometry.getAllMaterials()
num_groups = self.input_set.geometry.getNumEnergyGroups()
# Aggregate the total cross sections for each Material
# into a dictionary to pass to the mesh tally
domains_to_coeffs = OrderedDict(
{'flux' : {},
'total' : {},
'nu-fission': {},
'scatter' : {}})
for material_id in materials:
for rxn in domains_to_coeffs:
domains_to_coeffs[rxn][material_id] = np.zeros(num_groups)
for group in range(num_groups):
domains_to_coeffs['flux'][material_id][group] = 1.
domains_to_coeffs['total'][material_id][group] = \
materials[material_id].getSigmaTByGroup(group+1)
domains_to_coeffs['nu-fission'][material_id][group] = \
materials[material_id].getNuSigmaFByGroup(group+1)
# Add up reaction rates for scattering to all energy groups
scatter = 0
for gprime in range(num_groups):
scatter += materials[material_id].getSigmaSByGroup(
group + 1, gprime + 1)
domains_to_coeffs['scatter'][material_id][group] = scatter
# Tally volume-averaged OpenMOC rates on the Mesh
tallies = OrderedDict()
for rxn, coeffs in domains_to_coeffs.items():
tallies[rxn] = mesh.tally_on_mesh(self.solver, coeffs,
domain_type='material',
volume='integrated')
# Append reaction rates to the output string
for rxn, rates in tallies.items():
outstr += rxn.title() + ' Rate Mesh Tally\n'
rates = ['{0:12.6E}'.format(rate) for rate in rates.ravel()]
outstr += '\n'.join(rates) + '\n'
return outstr
track_generator.setNumThreads(num_threads)
track_generator.setSegmentFormation(openmoc.OTF_STACKS)
track_generator.setSegmentationZones([-32.13, -10.71, 10.71, 32.13])
track_generator.generateTracks()
###############################################################################
########################### Running a Simulation ##########################
###############################################################################
solver = openmoc.CPUSolver(track_generator)
solver.setConvergenceThreshold(tolerance)
solver.setNumThreads(num_threads)
solver.computeEigenvalue(max_iters)
solver.printTimerReport()
mesh = process.Mesh()
mesh.dimension = [34, 34, 3]
mesh.lower_left = [-32.13, -10.71, -32.13]
mesh.upper_right = [10.71, 32.13, 10.71]
mesh.width = [1.26, 1.26, 14.28]
fission_rates = mesh.tally_fission_rates(solver, volume='integrated')
for k in range(3):
print('Z = ' + str(k))
for i in range(34):
msg = ''
for j in range(34):
msg += str(fission_rates[i][j][k])
msg += ' '
print(msg)
print('...')