crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 14:15:42 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Respond to @wbinventor comments on #632

Browse source
This commit is contained in:
Paul Romano 2016-04-26 07:08:03 -05:00
parent 6234c4e05e
commit 1e57cb8407
15 changed files with 146 additions and 138 deletions
Download patch file Download diff file Expand all files Collapse all files

8
examples/python/lattice/simple/build-xml.py
View file

@ -30,7 +30,7 @@ moderator.add_nuclide(h1, 2.)
moderator.add_nuclide(o16, 1.)
moderator.add_s_alpha_beta('HH2O', '71t')
# Instantiate a Materials object, register all Materials, and export to XML
# Instantiate a Materials collection, register all Materials, and export to XML
materials_file = openmc.Materials()
materials_file.default_xs = '71c'
materials_file.add_materials([moderator, fuel])
@ -106,7 +106,7 @@ lattice.universes = [[univ1, univ2, univ1, univ2],
# Fill Cell with the Lattice
cell1.fill = lattice
# Instantiate a Geometry and register the root Universe, and export to XML
# Instantiate a Geometry, register the root Universe, and export to XML
geometry = openmc.Geometry()
geometry.root_universe = root
geometry.export_to_xml()
@ -142,7 +142,7 @@ plot.width = [4, 4]
plot.pixels = [400, 400]
plot.color = 'mat'
# Instantiate a Plots object, add Plot, and export to XML
# Instantiate a Plots collection, add Plot, and export to XML
plot_file = openmc.Plots()
plot_file.add_plot(plot)
plot_file.export_to_xml()
@ -173,7 +173,7 @@ tally.filters = [mesh_filter]
tally.scores = ['total']
tally.triggers = [trigger]
# Instantiate a Tallies object, register Tally/Mesh, and export to XML
# Instantiate a Tallies collection, register Tally/Mesh, and export to XML
tallies_file = openmc.Tallies()
tallies_file.add_mesh(mesh)
tallies_file.add_tally(tally)