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Respond to @drewejohnson comments on #1320

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This commit is contained in:
Paul Romano 2019-08-23 13:17:03 -05:00
parent 37c0fff7ed
commit 12ec18796a
3 changed files with 5 additions and 11 deletions
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8
tests/regression_tests/lattice_multiple/test.py
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@ -22,12 +22,8 @@ def model():
cyl = openmc.ZCylinder(r=0.4)
big_cyl = openmc.ZCylinder(r=0.5)
c1 = openmc.Cell(fill=uo2, region=-cyl)
c2 = openmc.Cell(fill=water, region=+cyl)
pin = openmc.Universe(cells=[c1, c2])
c3 = openmc.Cell(fill=uo2, region=-big_cyl)
c4 = openmc.Cell(fill=water, region=+big_cyl)
big_pin = openmc.Universe(cells=[c3, c4])
pin = openmc.model.pin([cyl], [uo2, water])
big_pin = openmc.model.pin([big_cyl], [uo2, water])
d = 1.2
inner_lattice = openmc.RectLattice()

6
tests/regression_tests/tally_aggregation/test.py
View file

@ -24,9 +24,7 @@ def model():
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])
pin = openmc.model.pin([cyl], [fuel, water])
d = 1.2
lattice = openmc.RectLattice()
lattice.lower_left = (-d, -d)
@ -45,7 +43,7 @@ def model():
model.settings.particles = 1000
energy_filter = openmc.EnergyFilter([0.0, 0.253, 1.0e3, 1.0e6, 20.0e6])
distrib_filter = openmc.DistribcellFilter(c1)
distrib_filter = openmc.DistribcellFilter(pin.cells[1])
tally = openmc.Tally(name='distribcell tally')
tally.filters = [energy_filter, distrib_filter]
tally.scores = ['nu-fission', 'total']

2
tests/regression_tests/tally_assumesep/tallies.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<tallies>
<assume_separate>false</assume_separate>
<assume_separate>true</assume_separate>
<filter id="1">
<type>cell</type>