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OpenMC Monte Carlo Code
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8
Last push
3mo ago
Recent commits
Latest commits.
All reduce to print correct number of surface source particles (#3901)
8223099
April Novak
3mo ago
Fix surface tally when crossing lattice (#3895)
6cd3907
GuySten
3mo ago
Add `fusion_neutron_spectrum` to openmc.stats module (#3862)
3ce6cbf
Paul Romano
3mo ago
Implement angular PDF evaluation for angle-energy distributions (#3550)
1578698
itay-space
3mo ago
get indices for rectilinear meshes (#3876)
bc9c31e
Marco De Pietri
3mo ago
Add properties to settings w/ documentation, c++ loading of filename, and python round-trip test (#3808)
dd6d31b
Paul Wilson
3mo ago
Allow `StepResult.get_material` to accept integer material ID (#3872)
4bda85f
AlvaroCubi
3mo ago
Allow groups to be passed as sequence of floats in `convert_to_multigroup` (#3873)
c44d2f0
Christopher Ashe
3mo ago
Top contributors
Builders behind this project.
paulromano
4.8K commits
pshriwise
1.7K commits
smharper
1K commits
nelsonag
831 commits
shimwell
470 commits
drewejohnson
318 commits
jtramm
286 commits
yardasol
205 commits