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added specialized fission-getting methods

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This commit is contained in:
Adam G Nelson 2018-09-02 18:59:28 -04:00
parent 35def7aac2
commit d6f94f7ce8
11 changed files with 678 additions and 368 deletions
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10
include/openmc/mgxs.h
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@ -159,7 +159,7 @@ class Mgxs {
//! @param dg delayed group index; use nullptr if irrelevant.
//! @return Requested cross section value.
double
get_xs(int xstype, int gin, int* gout, double* mu, int* dg);
get_xs(const int xstype, const int gin, int* gout, double* mu, int* dg);
//! \brief Samples the fission neutron energy and if prompt or delayed.
//!
@ -167,7 +167,7 @@ class Mgxs {
//! @param dg Sampled delayed group index.
//! @param gout Sampled outgoing energy group.
void
sample_fission_energy(int gin, int& dg, int& gout);
sample_fission_energy(const int gin, int& dg, int& gout);
//! \brief Samples the outgoing energy and angle from a scatter event.
//!
@ -176,7 +176,7 @@ class Mgxs {
//! @param mu Sampled cosine of the change-in-angle.
//! @param wgt Weight of the particle to be adjusted.
void
sample_scatter(int gin, int& gout, double& mu, double& wgt);
sample_scatter(const int gin, int& gout, double& mu, double& wgt);
//! \brief Calculates cross section quantities needed for tracking.
//!
@ -187,14 +187,14 @@ class Mgxs {
//! @param abs_xs Resultant absorption cross section.
//! @param nu_fiss_xs Resultant nu-fission cross section.
void
calculate_xs(int gin, double sqrtkT, const double uvw[3],
calculate_xs(const int gin, const double sqrtkT, const double uvw[3],
double& total_xs, double& abs_xs, double& nu_fiss_xs);
//! \brief Sets the temperature index in cache given a temperature
//!
//! @param sqrtkT Temperature of the material.
void
set_temperature_index(double sqrtkT);
set_temperature_index(const double sqrtkT);
//! \brief Sets the angle index in cache given a direction
//!

36
include/openmc/xsdata.h
View file

@ -33,6 +33,42 @@ class XsData {
fission_from_hdf5(hid_t xsdata_grp, size_t n_ang, size_t energy_groups,
size_t delayed_groups, bool is_isotropic);
//! \brief Reads fission data formatted as chi and nu-fission vectors from
// the HDF5 file when beta is provided.
void
fission_vector_beta_from_hdf5(hid_t xsdata_grp, size_t n_ang,
size_t energy_groups, size_t delayed_groups);
//! \brief Reads fission data formatted as chi and nu-fission vectors from
// the HDF5 file when beta is not provided.
void
fission_vector_no_beta_from_hdf5(hid_t xsdata_grp, size_t n_ang,
size_t energy_groups, size_t delayed_groups);
//! \brief Reads fission data formatted as chi and nu-fission vectors from
// the HDF5 file when no delayed data is provided.
void
fission_vector_no_delayed_from_hdf5(hid_t xsdata_grp, size_t n_ang,
size_t energy_groups);
//! \brief Reads fission data formatted as a nu-fission matrix from
// the HDF5 file when beta is provided.
void
fission_matrix_beta_from_hdf5(hid_t xsdata_grp, size_t n_ang,
size_t energy_groups, size_t delayed_groups);
//! \brief Reads fission data formatted as a nu-fission matrix from
// the HDF5 file when beta is not provided.
void
fission_matrix_no_beta_from_hdf5(hid_t xsdata_grp, size_t n_ang,
size_t energy_groups, size_t delayed_groups);
//! \brief Reads fission data formatted as a nu-fission matrix from
// the HDF5 file when no delayed data is provided.
void
fission_matrix_no_delayed_from_hdf5(hid_t xsdata_grp, size_t n_ang,
size_t energy_groups);
public:
// The following quantities have the following dimensions: