mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-25 12:35:29 -04:00
781dbf9c12
Co-authored-by: GuySten <guyste@post.bgu.ac.il> Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
44 lines
1.2 KiB
Python
44 lines
1.2 KiB
Python
"""Test the Iterated Fission Probability (IFP) method to compute adjoint-weighted
|
|
kinetics parameters using dedicated tallies."""
|
|
|
|
import openmc
|
|
import pytest
|
|
|
|
from tests.testing_harness import PyAPITestHarness
|
|
|
|
@pytest.fixture()
|
|
def ifp_model():
|
|
model = openmc.Model()
|
|
|
|
# Material
|
|
material = openmc.Material(name="core")
|
|
material.add_nuclide("U235", 1.0)
|
|
material.set_density('g/cm3', 16.0)
|
|
|
|
# Geometry
|
|
radius = 10.0
|
|
sphere = openmc.Sphere(r=radius, boundary_type="vacuum")
|
|
cell = openmc.Cell(region=-sphere, fill=material)
|
|
model.geometry = openmc.Geometry([cell])
|
|
|
|
# Settings
|
|
model.settings.particles = 1000
|
|
model.settings.batches = 20
|
|
model.settings.inactive = 5
|
|
model.settings.ifp_n_generation = 5
|
|
|
|
space = openmc.stats.Box(*cell.bounding_box)
|
|
model.settings.source = openmc.IndependentSource(
|
|
space=space, constraints={'fissionable': True})
|
|
|
|
# Tally IFP scores
|
|
tally = openmc.Tally(name="ifp-scores")
|
|
tally.scores = ["ifp-time-numerator", "ifp-beta-numerator", "ifp-denominator"]
|
|
model.tallies = [tally]
|
|
|
|
return model
|
|
|
|
|
|
def test_iterated_fission_probability(ifp_model):
|
|
harness = PyAPITestHarness("statepoint.20.h5", model=ifp_model)
|
|
harness.main()
|