OpenMC/tests/regression_tests/tally_aggregation/test.py
Paul Romano ac941f79e0
Add RectangularPrism and HexagonalPrism composite surfaces (#2739)
Co-authored-by: Patrick Shriwise <pshriwise@gmail.com>
2023-11-01 09:13:40 -05:00

97 lines
3.3 KiB
Python

import numpy as np
import openmc
import pytest
from tests.testing_harness import PyAPITestHarness
@pytest.fixture
def model():
model = openmc.model.Model()
fuel = openmc.Material(name='UO2')
fuel.set_density('g/cm3', 10.29769)
fuel.add_nuclide("U234", 4.4843e-6)
fuel.add_nuclide("U235", 5.5815e-4)
fuel.add_nuclide("U238", 2.2408e-2)
fuel.add_nuclide("O16", 4.5829e-2)
water = openmc.Material(name='light water')
water.add_nuclide('H1', 2.0)
water.add_nuclide('O16', 1.0)
water.set_density('g/cm3', 1.0)
water.add_s_alpha_beta('c_H_in_H2O')
model.materials.extend([fuel, water])
cyl = openmc.ZCylinder(r=0.4)
pin = openmc.model.pin([cyl], [fuel, water])
d = 1.2
lattice = openmc.RectLattice()
lattice.lower_left = (-d, -d)
lattice.pitch = (d, d)
lattice.outer = pin
lattice.universes = [
[pin, pin],
[pin, pin],
]
box = openmc.model.RectangularPrism(2*d, 2*d, boundary_type='reflective')
main_cell = openmc.Cell(fill=lattice, region=-box)
model.geometry = openmc.Geometry([main_cell])
model.settings.batches = 10
model.settings.inactive = 5
model.settings.particles = 1000
energy_filter = openmc.EnergyFilter([0.0, 0.253, 1.0e3, 1.0e6, 20.0e6])
distrib_filter = openmc.DistribcellFilter(pin.cells[1])
tally = openmc.Tally(name='distribcell tally')
tally.filters = [energy_filter, distrib_filter]
tally.scores = ['nu-fission', 'total']
tally.nuclides = ['U234', 'U235', 'U238']
model.tallies.append(tally)
return model
class TallyAggregationTestHarness(PyAPITestHarness):
def _get_results(self, hash_output=False):
"""Digest info in the statepoint and return as a string."""
# Read the statepoint file.
sp = openmc.StatePoint(self._sp_name)
# Extract the tally of interest
tally = sp.get_tally(name='distribcell tally')
# Perform tally aggregations across filter bins, nuclides and scores
outstr = ''
# This test occasionally fails in CI due to differences in the 8th
# significant digit. Lowering precision to 7 digits prevents failures
with np.printoptions(precision=7):
# Sum across all energy filter bins
tally_sum = tally.summation(filter_type=openmc.EnergyFilter)
outstr += ', '.join(map(str, tally_sum.mean))
outstr += ', '.join(map(str, tally_sum.std_dev))
# Sum across all distribcell filter bins
tally_sum = tally.summation(filter_type=openmc.DistribcellFilter)
outstr += ', '.join(map(str, tally_sum.mean))
outstr += ', '.join(map(str, tally_sum.std_dev))
# Sum across all nuclides
tally_sum = tally.summation(nuclides=['U234', 'U235', 'U238'])
outstr += ', '.join(map(str, tally_sum.mean))
outstr += ', '.join(map(str, tally_sum.std_dev))
# Sum across all scores
tally_sum = tally.summation(scores=['nu-fission', 'total'])
outstr += ', '.join(map(str, tally_sum.mean))
outstr += ', '.join(map(str, tally_sum.std_dev))
return outstr
def test_tally_aggregation(model):
harness = TallyAggregationTestHarness('statepoint.10.h5', model)
harness.main()