OpenMC/tests/unit_tests/test_heating_by_nuclide.py
2022-06-02 15:49:10 -05:00

57 lines
2.1 KiB
Python

import openmc
import pytest
from tests.testing_harness import config
@pytest.fixture
def model():
# Create simple sphere model
model = openmc.Model()
mat = openmc.Material()
mat.add_nuclide('U235', 1.0)
mat.add_nuclide('H1', 1.0)
mat.set_density('g/cm3', 5.0)
sph = openmc.Sphere(r=10.0, boundary_type='vacuum')
cell = openmc.Cell(fill=mat, region=-sph)
model.geometry = openmc.Geometry([cell])
model.settings.particles = 1000
model.settings.inactive = 0
model.settings.batches = 5
model.settings.photon_transport = True
# Add two tallies, one with heating by nuclide and one with total heating
particle_filter = openmc.ParticleFilter(['neutron', 'photon'])
heating_by_nuclide = openmc.Tally()
heating_by_nuclide.filters = [particle_filter]
heating_by_nuclide.nuclides = ['U235', 'H1']
heating_by_nuclide.scores = ['heating']
heating_total = openmc.Tally()
heating_total.filters = [particle_filter]
heating_total.scores = ['heating']
model.tallies.extend([heating_by_nuclide, heating_total])
return model
def test_heating_by_nuclide(model, run_in_tmpdir):
# If running in MPI mode, setup proper keyword arguments for run()
kwargs = {'openmc_exec': config['exe']}
if config['mpi']:
kwargs['mpi_args'] = [config['mpiexec'], '-n', config['mpi_np']]
sp_path = model.run(**kwargs)
# Get tallies from resulting statepoint
with openmc.StatePoint(sp_path) as sp:
heating_by_nuclide = sp.tallies[model.tallies[0].id]
heating_total = sp.tallies[model.tallies[1].id]
for particle in heating_by_nuclide.filters[0].bins:
# Get slice of each tally corresponding to a single particle
kwargs = {'filters': [openmc.ParticleFilter], 'filter_bins': [(particle,)]}
particle_slice_by_nuclide = heating_by_nuclide.get_values(**kwargs)
particle_slice_total = heating_total.get_values(**kwargs)
# Summing over nuclides should equal total
assert particle_slice_by_nuclide.sum() == pytest.approx(particle_slice_total.sum())