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87 lines
2.9 KiB
C++
87 lines
2.9 KiB
C++
//! \file reaction.h
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//! Data for an incident neutron reaction
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#ifndef OPENMC_REACTION_H
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#define OPENMC_REACTION_H
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#include <string>
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#include "hdf5.h"
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#include "openmc/particle_data.h"
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#include "openmc/reaction_product.h"
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#include "openmc/span.h"
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#include "openmc/vector.h"
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namespace openmc {
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//==============================================================================
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//! Data for a single reaction including cross sections (possibly at multiple
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//! temperatures) and reaction products (with secondary angle-energy
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//! distributions)
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//==============================================================================
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class Reaction {
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public:
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//! Construct reaction from HDF5 data
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//! \param[in] group HDF5 group containing reaction data
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//! \param[in] temperatures Desired temperatures for cross sections
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//! \param[in] name Name of the nuclide
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explicit Reaction(
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hid_t group, const vector<int>& temperatures, std::string name);
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//! Calculate cross section given temperautre/grid index, interpolation factor
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//
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//! \param[in] i_temp Temperature index
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//! \param[in] i_grid Energy grid index
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//! \param[in] interp_factor Interpolation factor between grid points
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double xs(int64_t i_temp, int64_t i_grid, double interp_factor) const;
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//! Calculate cross section
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//
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//! \param[in] micro Microscopic cross section cache
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double xs(const NuclideMicroXS& micro) const;
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//! \brief Calculate reaction rate based on group-wise flux distribution
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//
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//! \param[in] i_temp Temperature index
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//! \param[in] energy Energy group boundaries in [eV]
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//! \param[in] flux Flux in each energy group (not normalized per eV)
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//! \param[in] grid Nuclide energy grid
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//! \return Reaction rate
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double collapse_rate(int64_t i_temp, span<const double> energy,
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span<const double> flux, const vector<double>& grid) const;
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//! Cross section at a single temperature
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struct TemperatureXS {
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int threshold;
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vector<double> value;
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};
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int mt_; //!< ENDF MT value
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double q_value_; //!< Reaction Q value in [eV]
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bool scatter_in_cm_; //!< scattering system in center-of-mass?
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bool redundant_; //!< redundant reaction?
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vector<TemperatureXS> xs_; //!< Cross section at each temperature
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vector<ReactionProduct> products_; //!< Reaction products
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};
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//==============================================================================
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// Non-member functions
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//==============================================================================
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//! Return reaction name given an ENDF MT value
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//
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//! \param[in] mt ENDF MT value
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//! \return Name of the corresponding reaction
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std::string reaction_name(int mt);
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//! Return reaction type (MT value) given a reaction name
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//
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//! \param[in] name Reaction name
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//! \return Corresponding reaction type (MT value)
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int reaction_type(std::string name);
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} // namespace openmc
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#endif // OPENMC_REACTION_H
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