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Convert ACE data from MeV to eV

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This commit is contained in:
Paul Romano 2016-10-24 18:44:51 -05:00
parent b50a9db628
commit 6da9f16d29
44 changed files with 219 additions and 212 deletions
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4
examples/python/basic/build-xml.py
View file

@ -101,8 +101,8 @@ settings_file.export_to_xml()
# Instantiate some tally Filters
cell_filter = openmc.CellFilter(100)
energy_filter = openmc.EnergyFilter([0., 20.])
energyout_filter = openmc.EnergyoutFilter([0., 20.])
energy_filter = openmc.EnergyFilter([0., 20.e6])
energyout_filter = openmc.EnergyoutFilter([0., 20.e6])
# Instantiate the first Tally
first_tally = openmc.Tally(tally_id=1, name='first tally')

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

@ -181,7 +181,7 @@ mesh.lower_left = [-0.62992, -0.62992, -1.e50]
mesh.upper_right = [0.62992, 0.62992, 1.e50]
# Instantiate some tally Filters
energy_filter = openmc.EnergyFilter([0., 4.e-6, 20.])
energy_filter = openmc.EnergyFilter([0., 4., 20.e6])
mesh_filter = openmc.MeshFilter(mesh)
# Instantiate the Tally

8
examples/python/pincell_multigroup/build-xml.py
View file

@ -15,8 +15,8 @@ particles = 1000
###############################################################################
# Instantiate the energy group data
groups = openmc.mgxs.EnergyGroups(group_edges=[1E-11, 0.0635E-6, 10.0E-6,
1.0E-4, 1.0E-3, 0.5, 1.0, 20.0])
groups = openmc.mgxs.EnergyGroups(group_edges=[
1e-5, 0.0635, 10.0, 1.0e2, 1.0e3, 0.5e6, 1.0e6, 20.0e6])
# Instantiate the 7-group (C5G7) cross section data
uo2_xsdata = openmc.XSdata('UO2', groups)
@ -156,8 +156,8 @@ mesh.lower_left = [-0.63, -0.63, -1.e50]
mesh.upper_right = [0.63, 0.63, 1.e50]
# Instantiate some tally Filters
energy_filter = openmc.EnergyFilter([1E-11, 0.0635E-6, 10.0E-6, 1.0E-4, 1.0E-3,
0.5, 1.0, 20.0])
energy_filter = openmc.EnergyFilter([1e-5, 0.0635, 10.0, 1.0e2, 1.0e3, 0.5e6,
1.0e6, 20.0e6])
mesh_filter = openmc.MeshFilter(mesh)
# Instantiate the Tally