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Namespace mgxs-related global variables

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This commit is contained in:
Paul Romano 2018-11-08 15:00:40 -06:00
parent 5fae5ffa9e
commit c301612ca2
9 changed files with 58 additions and 50 deletions
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4
include/openmc/mgxs_interface.h
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@ -15,6 +15,8 @@ namespace openmc {
// Global variables
//==============================================================================
namespace data {
extern std::vector<Mgxs> nuclides_MG;
extern std::vector<Mgxs> macro_xs;
extern "C" int num_energy_groups;
@ -22,6 +24,8 @@ extern std::vector<double> energy_bins;
extern std::vector<double> energy_bin_avg;
extern std::vector<double> rev_energy_bins;
} // namespace data
//==============================================================================
// Mgxs data loading interface methods
//==============================================================================

13
include/openmc/physics_mg.h
View file

@ -10,34 +10,29 @@
namespace openmc {
//TODO: Remove energy_bin_avg and material_xs parameters when they reside on
//TODO: Remove material_xs parameters when they reside on
// the C-side this should happen after materials, physics, input, and tallies
// are brought over
//! \brief samples particle behavior after a collision event.
//! \param p Particle to operate on
//! \param energy_bin_avg Average energy within each energy bin
//! \param material_xs The cross section cache for the current material
extern "C" void
collision_mg(Particle* p, const double* energy_bin_avg,
const MaterialMacroXS* material_xs);
collision_mg(Particle* p, const MaterialMacroXS* material_xs);
//! \brief samples a reaction type.
//!
//! Note that there is special logic when suvival biasing is turned on since
//! fission and disappearance are treated implicitly.
//! \param p Particle to operate on
//! \param energy_bin_avg Average energy within each energy bin
//! \param material_xs The cross section cache for the current material
void
sample_reaction(Particle* p, const double* energy_bin_avg,
const MaterialMacroXS* material_xs);
sample_reaction(Particle* p, const MaterialMacroXS* material_xs);
//! \brief Samples the scattering event
//! \param p Particle to operate on
//! \param energy_bin_avg Average energy within each energy bin
void
scatter(Particle* p, const double* energy_bin_avg);
scatter(Particle* p);
//! \brief Determines the average total, prompt and delayed neutrons produced
//! from fission and creates the appropriate bank sites.