mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-21 14:35:27 -04:00
ace73ab5de
Co-authored-by: Jonathan Shimwell <drshimwell@gmail.com> Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
39 lines
1.2 KiB
Python
39 lines
1.2 KiB
Python
import openmc
|
|
from pytest import approx
|
|
|
|
|
|
def test_nuclide_heating(run_in_tmpdir):
|
|
mat = openmc.Material()
|
|
mat.add_nuclide("Li6", 0.5)
|
|
mat.add_nuclide("Li7", 0.5)
|
|
mat.set_density("g/cm3", 1.0)
|
|
|
|
sphere = openmc.Sphere(r=20, boundary_type="reflective")
|
|
inside_sphere = openmc.Cell(fill=mat, region=-sphere)
|
|
model = openmc.Model()
|
|
model.geometry = openmc.Geometry([inside_sphere])
|
|
|
|
model.settings.particles = 1000
|
|
model.settings.batches = 1
|
|
model.settings.photon_transport = True
|
|
model.settings.electron_treatment = "ttb"
|
|
model.settings.cutoff = {"energy_photon": 1000}
|
|
model.settings.run_mode = "fixed source"
|
|
model.settings.source = openmc.IndependentSource(
|
|
energy=openmc.stats.delta_function(10.0e6),
|
|
particle="photon"
|
|
)
|
|
|
|
# Create two tallies, one with heating by nuclide and one with total heating
|
|
tally1 = openmc.Tally()
|
|
tally1.scores = ["heating"]
|
|
tally1.nuclides = mat.get_nuclides()
|
|
tally2 = openmc.Tally()
|
|
tally2.scores = ["heating"]
|
|
model.tallies = [tally1, tally2]
|
|
|
|
# Run the model
|
|
model.run(apply_tally_results=True)
|
|
|
|
# Make sure the heating results are consistent
|
|
assert tally1.mean.sum() == approx(tally2.mean.sum())
|