Update tally_aggregation test

This commit is contained in:
Paul Romano 2019-08-15 15:45:35 -05:00
parent fa11bacde7
commit 7bc96c822c
3 changed files with 176 additions and 315 deletions

View file

@ -1,311 +1,45 @@
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View file

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View file

@ -1,26 +1,63 @@
import hashlib
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)
c1 = openmc.Cell(fill=fuel, region=-cyl)
c2 = openmc.Cell(fill=water, region=+cyl)
pin = openmc.Universe(cells=[c1, c2])
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.rectangular_prism(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(c1)
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 __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# Initialize the filters
energy_filter = openmc.EnergyFilter([0.0, 0.253, 1.0e3, 1.0e6, 20.0e6])
distrib_filter = openmc.DistribcellFilter(60)
# Initialized the tallies
tally = openmc.Tally(name='distribcell tally')
tally.filters = [energy_filter, distrib_filter]
tally.scores = ['nu-fission', 'total']
tally.nuclides = ['U234', 'U235', 'U238']
self._model.tallies.append(tally)
def _get_results(self, hash_output=True):
def _get_results(self, hash_output=False):
"""Digest info in the statepoint and return as a string."""
# Read the statepoint file.
@ -52,15 +89,9 @@ class TallyAggregationTestHarness(PyAPITestHarness):
outstr += ', '.join(map(str, tally_sum.mean))
outstr += ', '.join(map(str, tally_sum.std_dev))
# Hash the results if necessary
if hash_output:
sha512 = hashlib.sha512()
sha512.update(outstr.encode('utf-8'))
outstr = sha512.hexdigest()
return outstr
def test_tally_aggregation():
harness = TallyAggregationTestHarness('statepoint.10.h5')
def test_tally_aggregation(model):
harness = TallyAggregationTestHarness('statepoint.10.h5', model)
harness.main()