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simplified interface for creating fission sites

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This commit is contained in:
John Tramm 2020-01-13 20:03:18 +00:00
parent b41f3aadb4
commit 58e3d3a275
4 changed files with 30 additions and 21 deletions
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3
include/openmc/physics.h
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@ -48,8 +48,7 @@ int sample_nuclide(Particle* p);
//! Determine the average total, prompt, and delayed neutrons produced from
//! fission and creates appropriate bank sites.
void create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx,
std::vector<Particle::Bank>& bank, bool use_fission_bank);
void create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx);
int sample_element(Particle* p);

2
include/openmc/physics_mg.h
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@ -36,7 +36,7 @@ scatter(Particle* p);
//! \param bank The particle bank to populate
//! \param use_fission_bank Indicates if shared global fission bank should be used
void
create_fission_sites(Particle* p, std::vector<Particle::Bank>& bank, bool use_fission_bank);
create_fission_sites(Particle* p);
//! \brief Handles an absorption event
//! \param p Particle to operate on