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Updated to get significantly higher tets passage rate. Still have more work to do in a few key areas.

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This commit is contained in:
Adam Nelson 2016-08-21 20:40:47 -04:00
parent 6a44a68975
commit cd95667292
94 changed files with 385 additions and 314 deletions
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4
examples/python/boxes/build-xml.py
View file

@ -34,11 +34,11 @@ moderator = openmc.Material(material_id=3, name='moderator')
moderator.set_density('g/cc', 1.0)
moderator.add_nuclide(h1, 2.)
moderator.add_nuclide(o16, 1.)
moderator.add_s_alpha_beta('c_H_in_H2O', '71t')
moderator.add_s_alpha_beta('c_H_in_H2O')
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([fuel1, fuel2, moderator])
materials_file.default_xs = '71c'
materials_file.default_temperature = '294K'
materials_file.export_to_xml()

4
examples/python/lattice/hexagonal/build-xml.py
View file

@ -29,7 +29,7 @@ moderator = openmc.Material(material_id=2, name='moderator')
moderator.set_density('g/cc', 1.0)
moderator.add_nuclide(h1, 2.)
moderator.add_nuclide(o16, 1.)
moderator.add_s_alpha_beta('c_H_in_H2O', '71t')
moderator.add_s_alpha_beta('c_H_in_H2O')
iron = openmc.Material(material_id=3, name='iron')
iron.set_density('g/cc', 7.9)
@ -37,7 +37,7 @@ iron.add_nuclide(fe56, 1.)
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([moderator, fuel, iron])
materials_file.default_xs = '71c'
materials_file.default_temperature = '294K'
materials_file.export_to_xml()

4
examples/python/lattice/nested/build-xml.py
View file

@ -28,11 +28,11 @@ moderator = openmc.Material(material_id=2, name='moderator')
moderator.set_density('g/cc', 1.0)
moderator.add_nuclide(h1, 2.)
moderator.add_nuclide(o16, 1.)
moderator.add_s_alpha_beta('c_H_in_H2O', '71t')
moderator.add_s_alpha_beta('c_H_in_H2O')
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials((moderator, fuel))
materials_file.default_xs = '71c'
materials_file.default_temperature = '294K'
materials_file.export_to_xml()

4
examples/python/lattice/simple/build-xml.py
View file

@ -28,11 +28,11 @@ moderator = openmc.Material(material_id=2, name='moderator')
moderator.set_density('g/cc', 1.0)
moderator.add_nuclide(h1, 2.)
moderator.add_nuclide(o16, 1.)
moderator.add_s_alpha_beta('c_H_in_H2O', '71t')
moderator.add_s_alpha_beta('c_H_in_H2O')
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([moderator, fuel])
materials_file.default_xs = '71c'
materials_file.default_temperature = '294K'
materials_file.export_to_xml()

4
examples/python/pincell/build-xml.py
View file

@ -98,11 +98,11 @@ borated_water.add_nuclide(h1, 4.9457e-2)
borated_water.add_nuclide(h2, 7.4196e-6)
borated_water.add_nuclide(o16, 2.4672e-2)
borated_water.add_nuclide(o17, 6.0099e-5)
borated_water.add_s_alpha_beta('c_H_in_H2O', '71t')
borated_water.add_s_alpha_beta('c_H_in_H2O')
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([uo2, helium, zircaloy, borated_water])
materials_file.default_xs = '71c'
materials_file.default_temperature = '294K'
materials_file.export_to_xml()

2
examples/python/reflective/build-xml.py
View file

@ -25,7 +25,7 @@ fuel.add_nuclide(u235, 1.)
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([fuel])
materials_file.default_xs = '71c'
materials_file.default_temperature = '294K'
materials_file.export_to_xml()

4
examples/xml/basic/materials.xml
View file

@ -1,12 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<material id="40">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
<temperature>294K</temperature>
</material>
<material id="41">
@ -14,7 +13,6 @@
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<sab name="c_H_in_H2O"/>
<temperature>294K</temperature>
</material>
</materials>

4
examples/xml/boxes/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
@ -17,7 +17,7 @@
<density value="1.0" units="g/cc" />
<nuclide name="O16" ao="1.0" />
<nuclide name="H1" ao="2.0" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

4
examples/xml/lattice/nested/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Definition of materials -->
<material id="1">
@ -13,7 +13,7 @@
<density value="1.0" units="g/cc" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

4
examples/xml/lattice/simple/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Definition of materials -->
<material id="1">
@ -13,7 +13,7 @@
<density value="1.0" units="g/cc" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

6
examples/xml/pincell/materials.xml
View file

@ -1,8 +1,8 @@
<?xml version="1.0"?>
<materials>
<!-- By default, use 300K cross sections -->
<default_xs>71c</default_xs>
<!-- By default, use 294K cross sections -->
<default_temperature>294K</default_temperature>
<!--
Since O-18 is not present in ENDF/B-VII, it was necessary to combine the
@ -64,7 +64,7 @@
<nuclide name="H2" ao="7.4196e-06" />
<nuclide name="O16" ao="2.4672e-02" />
<nuclide name="O17" ao="6.0099e-05" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

2
examples/xml/reflective/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />

12
openmc/summary.py
View file

@ -113,6 +113,7 @@ class Summary(object):
material_id = int(key.lstrip('material '))
index = self._f['materials'][key]['index'].value
name = self._f['materials'][key]['name'].value.decode()
temperature = self._f['materials'][key]['temperature'].value.decode()
density = self._f['materials'][key]['atom_density'].value
nuc_densities = self._f['materials'][key]['nuclide_densities'][...]
nuclides = self._f['materials'][key]['nuclides'].value
@ -124,22 +125,21 @@ class Summary(object):
if 'sab_names' in self._f['materials'][key]:
sab_tables = self._f['materials'][key]['sab_names'].value
for sab_table in sab_tables:
name, xs = sab_table.decode().split('.')
material.add_s_alpha_beta(name, xs)
name = sab_table.decode()
material.add_s_alpha_beta(name)
# Set the Material's density to atom/b-cm as used by OpenMC
material.set_density(density=density, units='atom/b-cm')
# Add all nuclides to the Material
for fullname, density in zip(nuclides, nuc_densities):
fullname = fullname.decode().strip()
name, xs = fullname.split('.')
name = fullname.decode().strip()
if 'nat' in name:
material.add_element(openmc.Element(name=name, xs=xs),
material.add_element(openmc.Element(name=name),
percent=density, percent_type='ao')
else:
material.add_nuclide(openmc.Nuclide(name=name, xs=xs),
material.add_nuclide(openmc.Nuclide(name=name),
percent=density, percent_type='ao')
# Add the Material to the global dictionary of all Materials

2
src/input_xml.F90
View file

@ -2211,7 +2211,7 @@ contains
else if (default_temperature /= '') then
mat % temperature = default_temperature
else
call fatal_error("Must specify eithe a material temperature or a &
call fatal_error("Must specify either a material temperature or a &
&default temperature")
end if

15
src/summary.F90
View file

@ -527,10 +527,13 @@ contains
call write_dataset(material_group, "index", i)
! Write name for this material
call write_dataset(material_group, "name", m%name)
call write_dataset(material_group, "name", m % name)
! Write temperature for this material
call write_dataset(material_group, "temperature", m % temperature)
! Write atom density with units
call write_dataset(material_group, "atom_density", m%density)
call write_dataset(material_group, "atom_density", m % density)
call write_attribute_string(material_group, "atom_density", "units", &
"atom/b-cm")
@ -572,7 +575,6 @@ contains
integer(HID_T), intent(in) :: file_id
integer :: i, j, k
integer :: i_xs
integer :: n_order ! loop index for moment orders
integer :: nm_order ! loop index for Ynm moment orders
integer(HID_T) :: tallies_group
@ -635,12 +637,7 @@ contains
allocate(str_array(t%n_nuclide_bins))
NUCLIDE_LOOP: do j = 1, t%n_nuclide_bins
if (t%nuclide_bins(j) > 0) then
i_xs = index(nuclides(t%nuclide_bins(j))%name, '.')
if (i_xs > 0) then
str_array(j) = nuclides(t%nuclide_bins(j))%name(1 : i_xs-1)
else
str_array(j) = nuclides(t%nuclide_bins(j))%name
end if
str_array(j) = nuclides(t % nuclide_bins(j)) % name
else
str_array(j) = 'total'
end if

2
tests/test_asymmetric_lattice/inputs_true.dat
View file

@ -1 +1 @@
a55899cd2ed0a8ec5d44003139da639f87f5f03ee76b2d6577db6a8c2014849e4277f8e68fa874ac6795e4cbc4eb6e4031d726cafe6e663e84787d1ecd8e7f86
7b62ec28ffec0028dc07ed23b720ae3f97b00aa15b319dc3991d9f1f88fcae8bffc7ccd2385d2b848180a57120624061ff4fe10745a3187e3e64fee0faface8d

8
tests/test_cmfd_feed/materials.xml
View file

@ -1,12 +1,14 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" xs="71c" wo="0.21" />
<nuclide name="U238" xs="71c" wo="0.68" />
<nuclide name="O16" xs="71c" wo="0.11" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

8
tests/test_cmfd_nofeed/materials.xml
View file

@ -1,12 +1,14 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" xs="71c" wo="0.21" />
<nuclide name="U238" xs="71c" wo="0.68" />
<nuclide name="O16" xs="71c" wo="0.11" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

2
tests/test_complex_cell/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />

3
tests/test_confidence_intervals/materials.xml
View file

@ -2,8 +2,9 @@
<materials>
<material id="1">
<temperature>294K</temperature>
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

14
tests/test_density/materials.xml
View file

@ -1,26 +1,28 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="0.1" units="atom/b-cm" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="4.5e22" units="atom/cm3" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="3">
<density value="12.3e3" units="kg/m3" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="4">
<density units="sum" />
<nuclide name="U235" xs="71c" ao="0.3e-2" />
<nuclide name="U238" xs="71c" ao="0.5e-1" />
<nuclide name="H1" xs="71c" ao="0.1e-2" />
<nuclide name="U235" ao="0.3e-2" />
<nuclide name="U238" ao="0.5e-1" />
<nuclide name="H1" ao="0.1e-2" />
</material>
</materials>

2
tests/test_distribmat/inputs_true.dat
View file

@ -1 +1 @@
46df57157980545d90b482acfb01f525b84c0e623fa93a5d9c08a65723d677ef1c092360219a3c7fcf5110c6ba32f1eacbd5c5eaed40be4bfe154f302400c0a4
6ae54c198e7659503d297e40be746a5bd72b35909fceed4b3ef357876b781946c0ea5021342556ef21f4034fa9e42b2c6014077c0efd3459dc063e6da4b12b59

2
tests/test_distribmat/test_distribmat.py
View file

@ -29,7 +29,7 @@ class DistribmatTestHarness(PyAPITestHarness):
light_fuel.add_nuclide('U235', 1.0)
mats_file = openmc.Materials([moderator, dense_fuel, light_fuel])
mats_file.default_xs = '71c'
mats_file.default_temperature = '294K'
mats_file.export_to_xml()

4
tests/test_eigenvalue_genperbatch/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_eigenvalue_no_inactive/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

8
tests/test_energy_grid/materials.xml
View file

@ -1,11 +1,13 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="H1" xs="71c" ao="0.5" />
<nuclide name="C0" xs="71c" ao="0.5" />
<nuclide name="U235" ao="1.0" />
<nuclide name="H1" ao="0.5" />
<nuclide name="C0" ao="0.5" />
</material>
</materials>

2
tests/test_energy_laws/materials.xml
View file

@ -1,6 +1,6 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="20" units="g/cc" />
<nuclide name="U233" ao="1.0" />

4
tests/test_entropy/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

2
tests/test_filter_distribcell/case-1/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Definition of materials -->
<material id="1">

2
tests/test_filter_distribcell/case-2/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Definition of materials -->
<material id="1">

2
tests/test_filter_distribcell/case-3/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Fuel composition -->
<material id="1">

27
tests/test_filter_distribcell/case-4/materials.xml
View file

@ -1,18 +1,21 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<default_xs>71c</default_xs>
<material id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<default_temperature>294K</default_temperature>
<material id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="moderator">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="2.0" name="H1" />
<sab name="c_H_in_H2O" xs="71t" />
<material id="2" name="moderator">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="2.0" name="H1" />
<sab name="c_H_in_H2O" />
</material>
<material id="3" name="iron">
<density units="g/cc" value="7.9" />
<nuclide ao="1.0" name="Fe56" />
<material id="3" name="iron">
<density units="g/cc" value="7.9" />
<nuclide ao="1.0" name="Fe56" />
</material>
</materials>

20
tests/test_filter_mesh_2d/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Fuel composition -->
<material id="1">
@ -59,7 +59,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Hot borated water -->
@ -69,7 +69,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- RPV Composition -->
@ -128,7 +128,7 @@
<nuclide name="Cr52" wo="0.145407678031" />
<nuclide name="Cr53" wo="0.016806340306" />
<nuclide name="Cr54" wo="0.004261520857" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Upper radial reflector / Top plate region -->
@ -155,7 +155,7 @@
<nuclide name="Cr52" wo="0.146766614995" />
<nuclide name="Cr53" wo="0.01696340737" />
<nuclide name="Cr54" wo="0.004301347765" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom plate region -->
@ -182,7 +182,7 @@
<nuclide name="Cr52" wo="0.157390026871" />
<nuclide name="Cr53" wo="0.018191270146" />
<nuclide name="Cr54" wo="0.004612692337" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom nozzle region -->
@ -209,7 +209,7 @@
<nuclide name="Cr52" wo="0.124142524198" />
<nuclide name="Cr53" wo="0.014348496148" />
<nuclide name="Cr54" wo="0.003638294506" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top nozzle region -->
@ -236,7 +236,7 @@
<nuclide name="Cr52" wo="0.107931450781" />
<nuclide name="Cr53" wo="0.012474806806" />
<nuclide name="Cr54" wo="0.003163190107" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top of Fuel Assemblies -->
@ -251,7 +251,7 @@
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom of Fuel Assemblies -->
@ -266,7 +266,7 @@
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

20
tests/test_filter_mesh_3d/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Fuel composition -->
<material id="1">
@ -59,7 +59,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Hot borated water -->
@ -69,7 +69,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- RPV Composition -->
@ -128,7 +128,7 @@
<nuclide name="Cr52" wo="0.145407678031" />
<nuclide name="Cr53" wo="0.016806340306" />
<nuclide name="Cr54" wo="0.004261520857" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Upper radial reflector / Top plate region -->
@ -155,7 +155,7 @@
<nuclide name="Cr52" wo="0.146766614995" />
<nuclide name="Cr53" wo="0.01696340737" />
<nuclide name="Cr54" wo="0.004301347765" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom plate region -->
@ -182,7 +182,7 @@
<nuclide name="Cr52" wo="0.157390026871" />
<nuclide name="Cr53" wo="0.018191270146" />
<nuclide name="Cr54" wo="0.004612692337" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom nozzle region -->
@ -209,7 +209,7 @@
<nuclide name="Cr52" wo="0.124142524198" />
<nuclide name="Cr53" wo="0.014348496148" />
<nuclide name="Cr54" wo="0.003638294506" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top nozzle region -->
@ -236,7 +236,7 @@
<nuclide name="Cr52" wo="0.107931450781" />
<nuclide name="Cr53" wo="0.012474806806" />
<nuclide name="Cr54" wo="0.003163190107" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top of Fuel Assemblies -->
@ -251,7 +251,7 @@
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom of Fuel Assemblies -->
@ -266,7 +266,7 @@
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

6
tests/test_fixed_source/materials.xml
View file

@ -1,10 +1,12 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="7.5" units="g/cc" />
<nuclide name="O16" xs="71c" ao="1.0" />
<nuclide name="U238" xs="71c" ao="0.0001" />
<nuclide name="O16" ao="1.0" />
<nuclide name="U238" ao="0.0001" />
</material>
</materials>

6
tests/test_infinite_cell/materials.xml
View file

@ -1,14 +1,16 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U238" xs="71c" ao="1.0" />
<nuclide name="U238" ao="1.0" />
</material>
</materials>

2
tests/test_iso_in_lab/inputs_true.dat
View file

@ -1 +1 @@
c05fdb7815ccc1dcd2f260429b9139ad96ad4a7d1643e2bb938e3cd61268451363538ef4e41c5eaf73a64dbace43b2bd4489d5ff012a33104c2c1d6fa61146eb
a84e601e6ba0891aaeaa37b1aa55076fecee598bb46be2b99dcdedab597b5d7e1731e2a0dc265df2ad6f475e33dae91a3cc27bc23d0c37be25a097ea83e74fd6

14
tests/test_lattice/materials.xml
View file

@ -10,7 +10,7 @@
===============================================================
-->
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- UO2-PuO2 Mixture -->
<material id="1">
@ -27,7 +27,7 @@
<nuclide name="U238" ao="2.0611e-02" />
<nuclide name="O16" ao="4.3779e-02" />
</material>
<!-- Natural UO2 Layer -->
<material id="2">
<density value="9.286" units="g/cm3" />
@ -37,7 +37,7 @@
<nuclide name="U238" ao="2.0525e-02" />
<nuclide name="O16" ao="4.1943e-02" />
</material>
<!-- Cladding -->
<material id="3">
<density units="sum" />
@ -75,7 +75,7 @@
<nuclide name="Zr94" ao="7.4075e-03" />
<nuclide name="Zr96" ao="1.1934e-03" />
</material>
<!-- Moderator -->
<material id="4">
<density units="sum" />
@ -88,9 +88,9 @@
<!-- Boron at 1.7 ppm -->
<nuclide name="B10" ao="1.8706e-08" />
<nuclide name="B11" ao="7.5770e-08" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- 6061 Aluminum -->
<material id="5">
<density units="sum" />
@ -128,7 +128,7 @@
<!-- Al at 5.8433e-2 atom/b-cm -->
<nuclide name="Al27" ao="5.8433e-02" />
</material>
<!-- Lead -->
<material id="6">
<density value="3.2174e-02" units="atom/b-cm" />

38
tests/test_lattice_hex/materials.xml
View file

@ -1,42 +1,44 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<!-- Material 01: Water -->
<material id="01">
<density value="0.998" units="g/cc"/>
<nuclide name="H1" xs="71c" ao="2.0"/>
<nuclide name="O16" xs="71c" ao="1.0"/>
<nuclide name="B10" xs="71c" ao="0.00085"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
<nuclide name="B10" ao="0.00085"/>
</material>
<!-- Material 13: Fuel (3.30%) -->
<material id="13">
<density value="10.371" units="g/cc"/>
<nuclide name="U235" xs="71c" ao="0.033408078"/>
<nuclide name="U238" xs="71c" ao="0.966591922"/>
<nuclide name="O16" xs="71c" ao="2.0"/>
<nuclide name="U235" ao="0.033408078"/>
<nuclide name="U238" ao="0.966591922"/>
<nuclide name="O16" ao="2.0"/>
</material>
<!-- Material 21: Zircaloy -->
<material id="21">
<density value="6.44" units="g/cc" />
<nuclide name="Zr90" xs="71c" wo="0.501807"/>
<nuclide name="Zr91" xs="71c" wo="0.110712"/>
<nuclide name="Zr92" xs="71c" wo="0.170991"/>
<nuclide name="Zr94" xs="71c" wo="0.177057"/>
<nuclide name="Zr96" xs="71c" wo="0.029133"/>
<nuclide name="Zr90" wo="0.501807"/>
<nuclide name="Zr91" wo="0.110712"/>
<nuclide name="Zr92" wo="0.170991"/>
<nuclide name="Zr94" wo="0.177057"/>
<nuclide name="Zr96" wo="0.029133"/>
</material>
<!-- Material 22: Steel -->
<material id="22">
<density value="7.9" units="g/cc"/>
<nuclide name="Mn55" xs="71c" wo="2"/>
<nuclide name="Ni58" xs="71c" wo="6.83"/>
<nuclide name="Ni60" xs="71c" wo="2.61"/>
<nuclide name="Cr53" xs="71c" wo="1.71"/>
<nuclide name="Fe54" xs="71c" wo="3.98257"/>
<nuclide name="Fe56" xs="71c" wo="63.03447"/>
<nuclide name="Fe57" xs="71c" wo="1.4763"/>
<nuclide name="Mn55" wo="2"/>
<nuclide name="Ni58" wo="6.83"/>
<nuclide name="Ni60" wo="2.61"/>
<nuclide name="Cr53" wo="1.71"/>
<nuclide name="Fe54" wo="3.98257"/>
<nuclide name="Fe56" wo="63.03447"/>
<nuclide name="Fe57" wo="1.4763"/>
</material>
</materials>

38
tests/test_lattice_mixed/materials.xml
View file

@ -1,42 +1,44 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<!-- Material 01: Water -->
<material id="01">
<density value="0.998" units="g/cc"/>
<nuclide name="H1" xs="71c" ao="2.0"/>
<nuclide name="O16" xs="71c" ao="1.0"/>
<nuclide name="B10" xs="71c" ao="0.00085"/>
<nuclide name="H1" ao="2.0"/>
<nuclide name="O16" ao="1.0"/>
<nuclide name="B10" ao="0.00085"/>
</material>
<!-- Material 13: Fuel (3.30%) -->
<material id="13">
<density value="10.371" units="g/cc"/>
<nuclide name="U235" xs="71c" ao="0.033408078"/>
<nuclide name="U238" xs="71c" ao="0.966591922"/>
<nuclide name="O16" xs="71c" ao="2.0"/>
<nuclide name="U235" ao="0.033408078"/>
<nuclide name="U238" ao="0.966591922"/>
<nuclide name="O16" ao="2.0"/>
</material>
<!-- Material 21: Zircaloy -->
<material id="21">
<density value="6.44" units="g/cc" />
<nuclide name="Zr90" xs="71c" wo="0.501807"/>
<nuclide name="Zr91" xs="71c" wo="0.110712"/>
<nuclide name="Zr92" xs="71c" wo="0.170991"/>
<nuclide name="Zr94" xs="71c" wo="0.177057"/>
<nuclide name="Zr96" xs="71c" wo="0.029133"/>
<nuclide name="Zr90" wo="0.501807"/>
<nuclide name="Zr91" wo="0.110712"/>
<nuclide name="Zr92" wo="0.170991"/>
<nuclide name="Zr94" wo="0.177057"/>
<nuclide name="Zr96" wo="0.029133"/>
</material>
<!-- Material 22: Steel -->
<material id="22">
<density value="7.9" units="g/cc"/>
<nuclide name="Mn55" xs="71c" wo="2"/>
<nuclide name="Ni58" xs="71c" wo="6.83"/>
<nuclide name="Ni60" xs="71c" wo="2.61"/>
<nuclide name="Cr53" xs="71c" wo="1.71"/>
<nuclide name="Fe54" xs="71c" wo="3.98257"/>
<nuclide name="Fe56" xs="71c" wo="63.03447"/>
<nuclide name="Fe57" xs="71c" wo="1.4763"/>
<nuclide name="Mn55" wo="2"/>
<nuclide name="Ni58" wo="6.83"/>
<nuclide name="Ni60" wo="2.61"/>
<nuclide name="Cr53" wo="1.71"/>
<nuclide name="Fe54" wo="3.98257"/>
<nuclide name="Fe56" wo="63.03447"/>
<nuclide name="Fe57" wo="1.4763"/>
</material>
</materials>

20
tests/test_lattice_multiple/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Fuel composition -->
<material id="1">
@ -59,7 +59,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Hot borated water -->
@ -69,7 +69,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- RPV Composition -->
@ -128,7 +128,7 @@
<nuclide name="Cr52" wo="0.145407678031" />
<nuclide name="Cr53" wo="0.016806340306" />
<nuclide name="Cr54" wo="0.004261520857" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Upper radial reflector / Top plate region -->
@ -155,7 +155,7 @@
<nuclide name="Cr52" wo="0.146766614995" />
<nuclide name="Cr53" wo="0.01696340737" />
<nuclide name="Cr54" wo="0.004301347765" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom plate region -->
@ -182,7 +182,7 @@
<nuclide name="Cr52" wo="0.157390026871" />
<nuclide name="Cr53" wo="0.018191270146" />
<nuclide name="Cr54" wo="0.004612692337" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom nozzle region -->
@ -209,7 +209,7 @@
<nuclide name="Cr52" wo="0.124142524198" />
<nuclide name="Cr53" wo="0.014348496148" />
<nuclide name="Cr54" wo="0.003638294506" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top nozzle region -->
@ -236,7 +236,7 @@
<nuclide name="Cr52" wo="0.107931450781" />
<nuclide name="Cr53" wo="0.012474806806" />
<nuclide name="Cr54" wo="0.003163190107" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top of Fuel Assemblies -->
@ -251,7 +251,7 @@
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom of Fuel Assemblies -->
@ -266,7 +266,7 @@
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

2
tests/test_mg_nuclide/inputs_true.dat
View file

@ -1 +1 @@
0efba3dd7882fdd38756d0a8f01ff00d7a1abdaab6430b3f090f3339e552448453bbb733852b6bd6ff09608d923c282f168320f942fc2eb3a45610873c588734
be296da93031694b2915e1a10e3e6fd663d612cdd29a84745e3ccb0065c088b4bcda45f6919962f6ee784efe52ebe178bf7d3ce019859637ae57c2da1e240a04

2
tests/test_mgxs_library_ce_to_mg/inputs_true.dat
View file

@ -1 +1 @@
fb9c9180f692198548ca14543b29a8b623b382a19932999b2140ca4dd440f2102ba2fdbcb500ede3b8829aa85e1b4498151d280f1422d2d6b1bb5789aff34d71
a33f770307b365103c5d71aa3e70deebd78d3a2fa90e88632641c1a40d64d19de0ce3c95c858aedf3beccc5de64cac434e1cd55b2b162ed315c78450c53a24a4

2
tests/test_mgxs_library_condense/inputs_true.dat
View file

@ -1 +1 @@
08c5f1c783dd88c5fed51c054718ca09fc4e99aa4560a6f928b3902991948f3a878d055ac46c07548904285c2c5f22dc2a3d8c1bb82b8e73d76dd790820117df
df2e5370925785e061e094561e9d2048c3104aaecf533ee9590a187d4597e53b489fb6e8cc54ed878f7d313bcf00586edceae4ff712c837faaa5ddab0ad378b3

2
tests/test_mgxs_library_distribcell/inputs_true.dat
View file

@ -1 +1 @@
9ce3d6987d67e92b0924916bb54288429d2bd6dfd12a69f86c5dbefb407f7eb72adb0e44d558c09e9a39610ffeb651aee4aedc629cf3a28a181d62ca4cfbcd5a
687358da3e7d658b6187e1d76280437d5b1a97a7ca3920483792e74de6fa9556fa86f4d55150c03d8628b3aa424afa187d8745f087f252ad0fca44ccc2a85f4c

2
tests/test_mgxs_library_hdf5/inputs_true.dat
View file

@ -1 +1 @@
08c5f1c783dd88c5fed51c054718ca09fc4e99aa4560a6f928b3902991948f3a878d055ac46c07548904285c2c5f22dc2a3d8c1bb82b8e73d76dd790820117df
df2e5370925785e061e094561e9d2048c3104aaecf533ee9590a187d4597e53b489fb6e8cc54ed878f7d313bcf00586edceae4ff712c837faaa5ddab0ad378b3

2
tests/test_mgxs_library_mesh/inputs_true.dat
View file

@ -1 +1 @@
5f167bdd4d6ae5873d48483e85aceaec8a934239ed5a50ef6f6500ce204f5851ae330621a5007f3b3d6bdab49f2cd627d011c1f6e6983fec958a6984eb9cb7ca
7f3aec9cedab76262de3706427ccba88b4c81fd4c9a033ff5467671ca21abe13b3981100d688502818bdd0534db22438970b02d652ca9d105557276de2d2a550

2
tests/test_mgxs_library_no_nuclides/inputs_true.dat
View file

@ -1 +1 @@
08c5f1c783dd88c5fed51c054718ca09fc4e99aa4560a6f928b3902991948f3a878d055ac46c07548904285c2c5f22dc2a3d8c1bb82b8e73d76dd790820117df
df2e5370925785e061e094561e9d2048c3104aaecf533ee9590a187d4597e53b489fb6e8cc54ed878f7d313bcf00586edceae4ff712c837faaa5ddab0ad378b3

2
tests/test_mgxs_library_nuclides/inputs_true.dat
View file

@ -1 +1 @@
e4a5f03ab6167e96462c4ef537533fe33b98d7878ae00824c5619356bda8d548b3c71af01ba8c88d5a9b46dd1471d331e6f678a164af922200f2ee3642be6340
332fd9ff1ca576410ffc6c0f3f03c00618fc863509dc3725f2f3a82134e2400de9c1edf2adc68cb8bce528789094f8eb468371e65cbc13efe76d76467ef291d9

2
tests/test_multipole/inputs_true.dat
View file

@ -1 +1 @@
c727431ebef7a5987dade28f4cd940c566142f97b5ce01fbf9343d680caf9056623f0fac550db64f8f1043fa2cd8230155cfcbbcaffd1ae92cede723974596d7
54044104d26e9aa90abcdb62290b598bd6ef0d46c3a9e509726ae7b20a7155471edd3e942b71f07b5c855ac1e451d58913a2f43fa971a8c4d56e569ae3b401ed

2
tests/test_multipole/test_multipole.py
View file

@ -24,7 +24,7 @@ class MultipoleTestHarness(PyAPITestHarness):
dense_fuel.add_nuclide('U235', 1.0)
mats_file = openmc.Materials([moderator, dense_fuel])
mats_file.default_xs = '71c'
mats_file.default_temperature = '294K'
mats_file.export_to_xml()

2
tests/test_natural_element/materials.xml
View file

@ -3,7 +3,7 @@
<!-- pu-met-fast-021 case 2 -->
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Plutonium -->
<material id="1">

4
tests/test_output/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_particle_restart_eigval/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="20.0" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_particle_restart_fixed/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="1.4" units="g/cc" />
<nuclide name="B10" xs="71c" ao="1.0" />
<nuclide name="B10" ao="1.0" />
</material>
</materials>

4
tests/test_periodic/test_periodic.py
View file

@ -13,7 +13,7 @@ class PeriodicTest(PyAPITestHarness):
water = openmc.Material(1)
water.add_nuclide('H1', 2.0)
water.add_nuclide('O16', 1.0)
water.add_s_alpha_beta('c_H_in_H2O', '71t')
water.add_s_alpha_beta('c_H_in_H2O')
water.set_density('g/cc', 1.0)
fuel = openmc.Material(2)
@ -21,7 +21,7 @@ class PeriodicTest(PyAPITestHarness):
fuel.set_density('g/cc', 4.5)
materials = openmc.Materials((water, fuel))
materials.default_xs = '71c'
materials.default_temperature = '294K'
materials.export_to_xml()
# Define geometry

8
tests/test_plot/materials.xml
View file

@ -1,19 +1,21 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="3">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_ptables_off/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

6
tests/test_quadric_surfaces/materials.xml
View file

@ -1,10 +1,12 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U238" xs="71c" ao="1.0" />
<nuclide name="U235" xs="71c" ao="0.06" />
<nuclide name="U238" ao="1.0" />
<nuclide name="U235" ao="0.06" />
</material>
</materials>

4
tests/test_reflective_plane/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_rotation/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

14
tests/test_salphabeta/materials.xml
View file

@ -1,20 +1,20 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
<nuclide name="H1" ao="1.0" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
<nuclide name="C0" ao="1.0" />
<sab name="c_Graphite" xs="71t" />
<sab name="c_Graphite" />
</material>
<material id="3">
@ -22,8 +22,8 @@
<nuclide name="U235" ao="1.0" />
<nuclide name="Be9" ao="1.0" />
<nuclide name="O16" ao="1.0" />
<sab name="c_Be_in_BeO" xs="71t" />
<sab name="c_O_in_BeO" xs="71t" />
<sab name="c_Be_in_BeO" />
<sab name="c_O_in_BeO" />
</material>
<material id="4">
@ -36,8 +36,8 @@
<nuclide name="Zr96" ao="0.05" />
<nuclide name="U235" ao="0.1" />
<nuclide name="U238" ao="0.15" />
<sab name="c_Zr_in_ZrH" xs="71t" />
<sab name="c_H_in_ZrH" xs="71t" />
<sab name="c_Zr_in_ZrH" />
<sab name="c_H_in_ZrH" />
</material>
</materials>

20
tests/test_score_current/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Fuel composition -->
<material id="1">
@ -59,7 +59,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Hot borated water -->
@ -69,7 +69,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- RPV Composition -->
@ -128,7 +128,7 @@
<nuclide name="Cr52" wo="0.145407678031" />
<nuclide name="Cr53" wo="0.016806340306" />
<nuclide name="Cr54" wo="0.004261520857" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Upper radial reflector / Top plate region -->
@ -155,7 +155,7 @@
<nuclide name="Cr52" wo="0.146766614995" />
<nuclide name="Cr53" wo="0.01696340737" />
<nuclide name="Cr54" wo="0.004301347765" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom plate region -->
@ -182,7 +182,7 @@
<nuclide name="Cr52" wo="0.157390026871" />
<nuclide name="Cr53" wo="0.018191270146" />
<nuclide name="Cr54" wo="0.004612692337" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom nozzle region -->
@ -209,7 +209,7 @@
<nuclide name="Cr52" wo="0.124142524198" />
<nuclide name="Cr53" wo="0.014348496148" />
<nuclide name="Cr54" wo="0.003638294506" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top nozzle region -->
@ -236,7 +236,7 @@
<nuclide name="Cr52" wo="0.107931450781" />
<nuclide name="Cr53" wo="0.012474806806" />
<nuclide name="Cr54" wo="0.003163190107" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top of Fuel Assemblies -->
@ -251,7 +251,7 @@
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom of Fuel Assemblies -->
@ -266,7 +266,7 @@
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

4
tests/test_seed/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_source/test_source.py
View file

@ -13,9 +13,9 @@ import openmc
class SourceTestHarness(PyAPITestHarness):
def _build_inputs(self):
mat1 = openmc.Material(material_id=1)
mat1 = openmc.Material(material_id=1, temperature='294K')
mat1.set_density('g/cm3', 4.5)
mat1.add_nuclide(openmc.Nuclide('U235', '71c'), 1.0)
mat1.add_nuclide(openmc.Nuclide('U235'), 1.0)
materials = openmc.Materials([mat1])
materials.export_to_xml()

4
tests/test_source_file/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_sourcepoint_batch/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_sourcepoint_interval/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_sourcepoint_latest/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_sourcepoint_restart/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_statepoint_batch/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_statepoint_interval/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_statepoint_restart/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_statepoint_sourcesep/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

6
tests/test_survival_biasing/materials.xml
View file

@ -1,10 +1,12 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="19.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="2.0" />
<nuclide name="U238" xs="71c" ao="1.0" />
<nuclide name="U235" ao="2.0" />
<nuclide name="U238" ao="1.0" />
</material>
</materials>

2
tests/test_tallies/inputs_true.dat
View file

@ -1 +1 @@
1bef757d276362fdcd9405096b4cdcbd894f9215ed406493486a45193729be446c9a12242c887f89b6e209ec5beaaacb04dee2fd61e72b4f5c6a8712b776ed6e
11adb9111f20950e28b1c1929ee4ca0c9a6b2524de89bef44a495b2fe8cda3a2acac9e87d64ddb5eba591c8d22289956cb1f024d31e05da3c9a4162b8c589d85

2
tests/test_tally_aggregation/inputs_true.dat
View file

@ -1 +1 @@
67daf0d74cddb40ecbbc7e3793a3302866adcb1617fe2dc454dd161c06105e65027523f5e5954d80b961ba6c6abf14114b8be5c4d5b7682eaddffc1288d3e7c8
bc17ba12ee5de7e6b0226e589be9044af725ff4e27683b765a9c75e5629176b5ca51d1e0306028ae90185d64644babf9ac22e4753f092b4b836790f4e162f9d0

2
tests/test_tally_arithmetic/inputs_true.dat
View file

@ -1 +1 @@
c8772a174e2162030f0315a318991085f1a5c0b054883a5f071d520e34f9ecf7d309f25700067bea8685e2b6324a19a003bd6f6ab38161ee87c95257b5a6ae69
6b59ea3a0dc0d25c590f724b8c051a54e8d7836467ba31b7da72b0574398e6c73160a180524952ea983b0e7a7de776d2d7102d280d5a4e7e3624bd76f6f42a09

20
tests/test_tally_assumesep/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Fuel composition -->
<material id="1">
@ -59,7 +59,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Hot borated water -->
@ -69,7 +69,7 @@
<nuclide name="O16" ao="1.0" />
<nuclide name="B10" ao="6.490e-4" />
<nuclide name="B11" ao="2.689e-3" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- RPV Composition -->
@ -128,7 +128,7 @@
<nuclide name="Cr52" wo="0.145407678031" />
<nuclide name="Cr53" wo="0.016806340306" />
<nuclide name="Cr54" wo="0.004261520857" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Upper radial reflector / Top plate region -->
@ -155,7 +155,7 @@
<nuclide name="Cr52" wo="0.146766614995" />
<nuclide name="Cr53" wo="0.01696340737" />
<nuclide name="Cr54" wo="0.004301347765" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom plate region -->
@ -182,7 +182,7 @@
<nuclide name="Cr52" wo="0.157390026871" />
<nuclide name="Cr53" wo="0.018191270146" />
<nuclide name="Cr54" wo="0.004612692337" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom nozzle region -->
@ -209,7 +209,7 @@
<nuclide name="Cr52" wo="0.124142524198" />
<nuclide name="Cr53" wo="0.014348496148" />
<nuclide name="Cr54" wo="0.003638294506" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top nozzle region -->
@ -236,7 +236,7 @@
<nuclide name="Cr52" wo="0.107931450781" />
<nuclide name="Cr53" wo="0.012474806806" />
<nuclide name="Cr54" wo="0.003163190107" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Top of Fuel Assemblies -->
@ -251,7 +251,7 @@
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
<!-- Bottom of Fuel Assemblies -->
@ -266,7 +266,7 @@
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" xs="71t" />
<sab name="c_H_in_H2O" />
</material>
</materials>

2
tests/test_tally_nuclides/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Plutonium -->
<material id="1">

2
tests/test_tally_slice_merge/inputs_true.dat
View file

@ -1 +1 @@
a17354ce54bcb5ce93e861ae95fd932c45fe60c733d999aa180d5dee636f43130fac5b003c615e23c65d44fe55f376ef4c86596b78603ab217d7e37fd694074d
6d9ebab08ccce003e6128c6346ffd80e69a957fab15e9a0e211771efa68b24f276e62781f8471c72072f9017380d7e821c38002c03689993efed45db9590c039

4
tests/test_trace/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

136
tests/test_track_output/materials.xml
View file

@ -1,95 +1,97 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<!-- material 1: Water with 1511 PPM -->
<material id="1">
<density value="0.99823" units="g/cc" />
<nuclide name="H1" xs="71c" ao="6.6737E-002" />
<nuclide name="O16" xs="71c" ao="3.3369E-002" />
<nuclide name="B10" xs="71c" ao="1.6769E-005" />
<nuclide name="B11" xs="71c" ao="6.7497E-005" />
<sab name="c_H_in_H2O" xs="71t" />
<nuclide name="H1" ao="6.6737E-002" />
<nuclide name="O16" ao="3.3369E-002" />
<nuclide name="B10" ao="1.6769E-005" />
<nuclide name="B11" ao="6.7497E-005" />
<sab name="c_H_in_H2O" />
</material>
<!-- material 2: Fuel (2.459 w/o with B-10 for impurities) -->
<material id="2">
<density value="10.24" units="g/cc" />
<nuclide name="U235" xs="71c" ao="5.6868E-004" />
<!-- <nuclide name="U234" xs="71c" ao="4.5689E-006" /> -->
<nuclide name="U238" xs="71c" ao="2.2268E-002" />
<nuclide name="O16" xs="71c" ao="4.5683E-002" />
<nuclide name="B10" xs="71c" ao="2.6055E-007" />
<nuclide name="U235" ao="5.6868E-004" />
<!-- <nuclide name="U234" ao="4.5689E-006" /> -->
<nuclide name="U238" ao="2.2268E-002" />
<nuclide name="O16" ao="4.5683E-002" />
<nuclide name="B10" ao="2.6055E-007" />
</material>
<!-- Zircaloy-4 -->
<material id="3">
<density value=" 6.55" units="g/cc" />
<nuclide name="O16" xs="71c" ao="3.0743e-04" />
<!-- <nuclide name="O17" xs="71c" ao="7.4887e-07" />-->
<!-- <nuclide name="Cr50" xs="71c" ao="3.2962e-06" />-->
<!-- <nuclide name="Cr52" xs="71c" ao="6.3564e-05" />-->
<!-- <nuclide name="Cr53" xs="71c" ao="7.2076e-06" />-->
<!-- <nuclide name="Cr54" xs="71c" ao="1.7941e-06" />-->
<!-- <nuclide name="Fe54" xs="71c" ao="8.6699e-06" />-->
<!-- <nuclide name="Fe56" xs="71c" ao="1.3610e-04" />-->
<!-- <nuclide name="Fe57" xs="71c" ao="3.1431e-06" />-->
<!-- <nuclide name="Fe58" xs="71c" ao="4.1829e-07" />-->
<nuclide name="Zr90" xs="71c" ao="2.1827e-02" />
<nuclide name="Zr91" xs="71c" ao="4.7600e-03" />
<nuclide name="Zr92" xs="71c" ao="7.2758e-03" />
<nuclide name="Zr94" xs="71c" ao="7.3734e-03" />
<nuclide name="Zr96" xs="71c" ao="1.1879e-03" />
<!-- <nuclide name="Sn112" xs="71c" ao="4.6735e-06" />-->
<!-- <nuclide name="Sn114" xs="71c" ao="3.1799e-06" />-->
<!-- <nuclide name="Sn115" xs="71c" ao="1.6381e-06" />-->
<!-- <nuclide name="Sn116" xs="71c" ao="7.0055e-05" />-->
<!-- <nuclide name="Sn117" xs="71c" ao="3.7003e-05" />-->
<!-- <nuclide name="Sn118" xs="71c" ao="1.1669e-04" />-->
<!-- <nuclide name="Sn119" xs="71c" ao="4.1387e-05" />-->
<!-- <nuclide name="Sn120" xs="71c" ao="1.5697e-04" />-->
<!-- <nuclide name="Sn122" xs="71c" ao="2.2308e-05" />-->
<!-- <nuclide name="Sn124" xs="71c" ao="2.7897e-05" />-->
<nuclide name="O16" ao="3.0743e-04" />
<!-- <nuclide name="O17" ao="7.4887e-07" />-->
<!-- <nuclide name="Cr50" ao="3.2962e-06" />-->
<!-- <nuclide name="Cr52" ao="6.3564e-05" />-->
<!-- <nuclide name="Cr53" ao="7.2076e-06" />-->
<!-- <nuclide name="Cr54" ao="1.7941e-06" />-->
<!-- <nuclide name="Fe54" ao="8.6699e-06" />-->
<!-- <nuclide name="Fe56" ao="1.3610e-04" />-->
<!-- <nuclide name="Fe57" ao="3.1431e-06" />-->
<!-- <nuclide name="Fe58" ao="4.1829e-07" />-->
<nuclide name="Zr90" ao="2.1827e-02" />
<nuclide name="Zr91" ao="4.7600e-03" />
<nuclide name="Zr92" ao="7.2758e-03" />
<nuclide name="Zr94" ao="7.3734e-03" />
<nuclide name="Zr96" ao="1.1879e-03" />
<!-- <nuclide name="Sn112" ao="4.6735e-06" />-->
<!-- <nuclide name="Sn114" ao="3.1799e-06" />-->
<!-- <nuclide name="Sn115" ao="1.6381e-06" />-->
<!-- <nuclide name="Sn116" ao="7.0055e-05" />-->
<!-- <nuclide name="Sn117" ao="3.7003e-05" />-->
<!-- <nuclide name="Sn118" ao="1.1669e-04" />-->
<!-- <nuclide name="Sn119" ao="4.1387e-05" />-->
<!-- <nuclide name="Sn120" ao="1.5697e-04" />-->
<!-- <nuclide name="Sn122" ao="2.2308e-05" />-->
<!-- <nuclide name="Sn124" ao="2.7897e-05" />-->
</material>
<!-- material 3: Fuel Aluminum 6061 cladding -->
<!-- <material id="3">-->
<!-- <density value="2.5052" units="g/cc" />-->
<!-- <nuclide name="Al27" xs="71c" ao="5.3985e-02" />-->
<!-- <nuclide name="Mn55" xs="71c" ao="4.1191e-05" />-->
<!-- <nuclide name="Mg24" xs="71c" ao="4.9031e-04" />-->
<!-- <nuclide name="Mg25" xs="71c" ao="6.2072e-05" />-->
<!-- <nuclide name="Mg26" xs="71c" ao="6.8341e-05" />-->
<!-- <nuclide name="Si28" xs="71c" ao="2.9726e-04" />-->
<!-- <nuclide name="Si29" xs="71c" ao="1.5094e-05" />-->
<!-- <nuclide name="Si30" xs="71c" ao="9.9499e-06" />-->
<!-- <nuclide name="Cr50" xs="71c" ao="2.5214e-06" />-->
<!-- <nuclide name="Cr52" xs="71c" ao="4.8622e-05" />-->
<!-- <nuclide name="Cr53" xs="71c" ao="5.5133e-06" />-->
<!-- <nuclide name="Cr54" xs="71c" ao="1.3724e-06" />-->
<!-- <nuclide name="Fe54" xs="71c" ao="1.1053e-05" />-->
<!-- <nuclide name="Fe56" xs="71c" ao="1.7351e-04" />-->
<!-- <nuclide name="Fe57" xs="71c" ao="4.0070e-06" />-->
<!-- <nuclide name="Fe58" xs="71c" ao="5.3326e-07" />-->
<!-- <nuclide name="Ti46" xs="71c" ao="3.8992e-06" />-->
<!-- <nuclide name="Ti47" xs="71c" ao="3.5164e-06" />-->
<!-- <nuclide name="Ti48" xs="71c" ao="3.4842e-05" />-->
<!-- <nuclide name="Ti49" xs="71c" ao="2.5569e-06" />-->
<!-- <nuclide name="Ti50" xs="71c" ao="2.4482e-06" />-->
<!-- <nuclide name="Cu63" xs="71c" ao="4.1054e-05" />-->
<!-- <nuclide name="Cu65" xs="71c" ao="1.8299e-05" />-->
<!-- <nuclide name="Al27" ao="5.3985e-02" />-->
<!-- <nuclide name="Mn55" ao="4.1191e-05" />-->
<!-- <nuclide name="Mg24" ao="4.9031e-04" />-->
<!-- <nuclide name="Mg25" ao="6.2072e-05" />-->
<!-- <nuclide name="Mg26" ao="6.8341e-05" />-->
<!-- <nuclide name="Si28" ao="2.9726e-04" />-->
<!-- <nuclide name="Si29" ao="1.5094e-05" />-->
<!-- <nuclide name="Si30" ao="9.9499e-06" />-->
<!-- <nuclide name="Cr50" ao="2.5214e-06" />-->
<!-- <nuclide name="Cr52" ao="4.8622e-05" />-->
<!-- <nuclide name="Cr53" ao="5.5133e-06" />-->
<!-- <nuclide name="Cr54" ao="1.3724e-06" />-->
<!-- <nuclide name="Fe54" ao="1.1053e-05" />-->
<!-- <nuclide name="Fe56" ao="1.7351e-04" />-->
<!-- <nuclide name="Fe57" ao="4.0070e-06" />-->
<!-- <nuclide name="Fe58" ao="5.3326e-07" />-->
<!-- <nuclide name="Ti46" ao="3.8992e-06" />-->
<!-- <nuclide name="Ti47" ao="3.5164e-06" />-->
<!-- <nuclide name="Ti48" ao="3.4842e-05" />-->
<!-- <nuclide name="Ti49" ao="2.5569e-06" />-->
<!-- <nuclide name="Ti50" ao="2.4482e-06" />-->
<!-- <nuclide name="Cu63" ao="4.1054e-05" />-->
<!-- <nuclide name="Cu65" ao="1.8299e-05" />-->
<!-- </material>-->
<!-- material 4: Control Rod Material -->
<material id="4">
<density value="2.2442" units="g/cc" />
<nuclide name="B10" xs="71c" ao="9.7491e-4" />
<nuclide name="B11" xs="71c" ao="3.9241e-3" />
<nuclide name="O16" xs="71c" ao="4.4829e-2" />
<!-- <nuclide name="Na23" xs="71c" ao="1.7444e-3" />-->
<!-- <nuclide name="Al27" xs="71c" ao="1.0018e-3" />-->
<!-- <nuclide name="Si28" xs="71c" ao="1.6884e-02" />-->
<!-- <nuclide name="Si29" xs="71c" ao="8.5730e-04" />-->
<!-- <nuclide name="Si30" xs="71c" ao="5.6513e-04" />-->
<nuclide name="B10" ao="9.7491e-4" />
<nuclide name="B11" ao="3.9241e-3" />
<nuclide name="O16" ao="4.4829e-2" />
<!-- <nuclide name="Na23" ao="1.7444e-3" />-->
<!-- <nuclide name="Al27" ao="1.0018e-3" />-->
<!-- <nuclide name="Si28" ao="1.6884e-02" />-->
<!-- <nuclide name="Si29" ao="8.5730e-04" />-->
<!-- <nuclide name="Si30" ao="5.6513e-04" />-->
</material>
</materials>

4
tests/test_translation/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

2
tests/test_trigger_batch_interval/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Plutonium -->
<material id="1">

2
tests/test_trigger_no_batch_interval/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Plutonium -->
<material id="1">

2
tests/test_trigger_no_status/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Plutonium -->
<material id="1">

2
tests/test_trigger_tallies/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Plutonium -->
<material id="1">

10
tests/test_triso/test_triso.py
View file

@ -27,12 +27,12 @@ class TRISOTestHarness(PyAPITestHarness):
porous_carbon = openmc.Material()
porous_carbon.set_density('g/cm3', 1.0)
porous_carbon.add_nuclide('C0', 1.0)
porous_carbon.add_s_alpha_beta('c_Graphite', '71t')
porous_carbon.add_s_alpha_beta('c_Graphite')
ipyc = openmc.Material()
ipyc.set_density('g/cm3', 1.90)
ipyc.add_nuclide('C0', 1.0)
ipyc.add_s_alpha_beta('c_Graphite', '71t')
ipyc.add_s_alpha_beta('c_Graphite')
sic = openmc.Material()
sic.set_density('g/cm3', 3.20)
@ -42,12 +42,12 @@ class TRISOTestHarness(PyAPITestHarness):
opyc = openmc.Material()
opyc.set_density('g/cm3', 1.87)
opyc.add_nuclide('C0', 1.0)
opyc.add_s_alpha_beta('c_Graphite', '71t')
opyc.add_s_alpha_beta('c_Graphite')
graphite = openmc.Material()
graphite.set_density('g/cm3', 1.1995)
graphite.add_nuclide('C0', 1.0)
graphite.add_s_alpha_beta('c_Graphite', '71t')
graphite.add_s_alpha_beta('c_Graphite')
# Create TRISO particles
spheres = [openmc.Sphere(R=r*1e-4)
@ -108,7 +108,7 @@ class TRISOTestHarness(PyAPITestHarness):
settings.export_to_xml()
mats = openmc.Materials([fuel, porous_carbon, ipyc, sic, opyc, graphite])
mats.default_xs = '71c'
mats.default_temperature = '294K'
mats.export_to_xml()

4
tests/test_uniform_fs/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

8
tests/test_union_energy_grids/materials.xml
View file

@ -1,11 +1,13 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="H1" xs="71c" ao="0.5" />
<nuclide name="C0" xs="71c" ao="0.5" />
<nuclide name="U235" ao="1.0" />
<nuclide name="H1" ao="0.5" />
<nuclide name="C0" ao="0.5" />
</material>
</materials>

4
tests/test_universe/materials.xml
View file

@ -1,9 +1,11 @@
<?xml version="1.0"?>
<materials>
<default_temperature>294K</default_temperature>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" xs="71c" ao="1.0" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

4
tests/test_void/materials.xml
View file

@ -3,7 +3,7 @@
<!-- pu-met-fast-019 -->
<default_xs>71c</default_xs>
<default_temperature>294K</default_temperature>
<!-- Plutonium -->
<material id="1">
@ -41,7 +41,7 @@
<nuclide name="Fe56" ao="4.6739e-05" />
<nuclide name="Fe57" ao="1.0794e-06" />
<nuclide name="Fe58" ao="1.4365e-07" />
<sab name="c_Be" xs="71t" />
<sab name="c_Be" />
</material>
<!-- Steel Diaphragm and Steel Shaft -->

4
tests/test_volume_calc/test_volume_calc.py
View file

@ -15,7 +15,7 @@ class VolumeTest(PyAPITestHarness):
water.add_nuclide('H1', 2.0)
water.add_nuclide('O16', 1.0)
water.add_nuclide('B10', 0.0001)
water.add_s_alpha_beta('c_H_in_H2O', '71t')
water.add_s_alpha_beta('c_H_in_H2O')
water.set_density('g/cc', 1.0)
fuel = openmc.Material(2)
@ -24,7 +24,7 @@ class VolumeTest(PyAPITestHarness):
fuel.set_density('g/cc', 4.5)
materials = openmc.Materials((water, fuel))
materials.default_xs = '71c'
materials.default_temperature = '294K'
materials.export_to_xml()
cyl = openmc.ZCylinder(1, R=1.0, boundary_type='vacuum')