OpenMC/include/openmc/reaction.h

//! \file reaction.h
//! Data for an incident neutron reaction

#ifndef OPENMC_REACTION_H
#define OPENMC_REACTION_H

#include <string>
#include <vector>

#include "hdf5.h"

#include "openmc/reaction_product.h"

namespace openmc {

//==============================================================================
//! Data for a single reaction including cross sections (possibly at multiple
//! temperatures) and reaction products (with secondary angle-energy
//! distributions)
//==============================================================================

class Reaction {
public:
  //! Construct reaction from HDF5 data
  //! \param[in] group HDF5 group containing reaction data
  //! \param[in] temperatures Desired temperatures for cross sections
  explicit Reaction(hid_t group, const std::vector<int>& temperatures);

  //! Cross section at a single temperature
  struct TemperatureXS {
    int threshold;
    std::vector<double> value;
  };

  int mt_;             //!< ENDF MT value
  double q_value_;     //!< Reaction Q value in [eV]
  bool scatter_in_cm_; //!< scattering system in center-of-mass?
  bool redundant_;     //!< redundant reaction?
  std::vector<TemperatureXS> xs_; //!< Cross section at each temperature
  std::vector<ReactionProduct> products_; //!< Reaction products
};

//==============================================================================
// Non-member functions
//==============================================================================

std::string reaction_name(int mt);

} // namespace openmc

#endif // OPENMC_REACTION_H