crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-26 05:05:30 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Major refactor to include cross sections at multiple temperatures within the

Browse source 
Nuclide and SAlphaData derived types.
This commit is contained in:
Paul Romano 2016-08-29 10:16:59 -05:00
parent 4448d17ee1
commit a95266ab22
121 changed files with 1670 additions and 2213 deletions
Download patch file Download diff file Expand all files Collapse all files

1
examples/python/basic/build-xml.py
View file

@ -33,7 +33,6 @@ fuel.add_nuclide(u235, 1.)
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([moderator, fuel])
materials_file.default_temperature = '294K'
materials_file.export_to_xml()