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38 lines
1.1 KiB
C++
38 lines
1.1 KiB
C++
//! \file physics_mg.h
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//! Methods needed to perform the collision physics for multi-group mode
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#ifndef OPENMC_PHYSICS_MG_H
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#define OPENMC_PHYSICS_MG_H
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#include "openmc/capi.h"
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#include "openmc/nuclide.h"
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#include "openmc/particle.h"
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namespace openmc {
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//! \brief samples particle behavior after a collision event.
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//! \param p Particle to operate on
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void collision_mg(Particle& p);
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//! \brief samples a reaction type.
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//!
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//! Note that there is special logic when suvival biasing is turned on since
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//! fission and disappearance are treated implicitly.
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//! \param p Particle to operate on
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void sample_reaction(Particle& p);
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//! \brief Samples the scattering event
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//! \param p Particle to operate on
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void scatter(Particle& p);
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//! \brief Determines the average total, prompt and delayed neutrons produced
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//! from fission and creates the appropriate bank sites.
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//! \param p Particle to operate on
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void create_fission_sites(Particle& p);
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//! \brief Handles an absorption event
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//! \param p Particle to operate on
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void absorption(Particle& p);
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} // namespace openmc
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#endif // OPENMC_PHYSICS_MG_H
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