crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 22:26:08 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

save event nuclide rather than event element so that it is compatible with nuclide tally filters

Browse source
This commit is contained in:
liangjg 2019-04-10 16:43:25 -04:00
parent e7ab0b704c
commit a795de2db5
2 changed files with 14 additions and 9 deletions
Download patch file Download diff file Expand all files Collapse all files

2
include/openmc/physics.h
View file

@ -44,7 +44,7 @@ void sample_positron_reaction(Particle* p);
//!
//! \param[in] p Particle
//! \return Index in the data::nuclides vector
int sample_nuclide(const Particle* p);
int sample_nuclide(Particle* p);
//! Determine the average total, prompt, and delayed neutrons produced from
//! fission and creates appropriate bank sites.