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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()