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Update examples

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This commit is contained in:
Sterling Harper 2016-09-22 03:00:49 -04:00
parent 57371d217a
commit 7419cd26b3
15 changed files with 639 additions and 554 deletions
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6
examples/python/basic/build-xml.py
View file

@ -100,9 +100,9 @@ settings_file.export_to_xml()
###############################################################################
# Instantiate some tally Filters
cell_filter = openmc.Filter(type='cell', bins=100)
energy_filter = openmc.Filter(type='energy', bins=[0., 20.])
energyout_filter = openmc.Filter(type='energyout', bins=[0., 20.])
cell_filter = openmc.CellFilter(100)
energy_filter = openmc.EnergyFilter([0., 20.])
energyout_filter = openmc.EnergyoutFilter([0., 20.])
# Instantiate the first Tally
first_tally = openmc.Tally(tally_id=1, name='first tally')

2
examples/python/lattice/hexagonal/build-xml.py
View file

@ -159,7 +159,7 @@ plot_file.export_to_xml()
# Instantiate a distribcell Tally
tally = openmc.Tally(tally_id=1)
tally.filters = [openmc.Filter(type='distribcell', bins=[cell2.id])]
tally.filters = [openmc.DistribcellFilter(cell2.id)]
tally.scores = ['total']
# Instantiate a Tallies collection and export to XML

2
examples/python/lattice/nested/build-xml.py
View file

@ -162,7 +162,7 @@ mesh.lower_left = [-2, -2]
mesh.width = [1, 1]
# Instantiate tally Filter
mesh_filter = openmc.Filter()
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
# Instantiate the Tally

2
examples/python/lattice/simple/build-xml.py
View file

@ -155,7 +155,7 @@ mesh.lower_left = [-2, -2]
mesh.width = [1, 1]
# Instantiate tally Filter
mesh_filter = openmc.Filter()
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
# Instantiate tally Trigger

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

@ -185,8 +185,8 @@ 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.Filter(type='energy', bins=[0., 4.e-6, 20.])
mesh_filter = openmc.Filter()
energy_filter = openmc.EnergyFilter([0., 4.e-6, 20.])
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
# Instantiate the Tally

5
examples/python/pincell_multigroup/build-xml.py
View file

@ -153,10 +153,9 @@ 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.Filter(type='energy',
bins=[1E-11, 0.0635E-6, 10.0E-6, 1.0E-4, 1.0E-3,
energy_filter = openmc.EnergyFilter([1E-11, 0.0635E-6, 10.0E-6, 1.0E-4, 1.0E-3,
0.5, 1.0, 20.0])
mesh_filter = openmc.Filter()
mesh_filter = openmc.MeshFilter(mesh.id)
mesh_filter.mesh = mesh
# Instantiate the Tally