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Merge pull request #2381 from paulromano/anisotropic-fission

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Use correct direction for anisotropic fission and update numpy version for tests
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Patrick Shriwise 2023-02-20 12:37:08 -06:00 • committed by GitHub
commit a528de2976
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117 changed files with 13655 additions and 35684 deletions
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4
include/openmc/physics.h
View file

@ -87,8 +87,8 @@ Direction sample_target_velocity(const Nuclide& nuc, double E, Direction u,
Direction sample_cxs_target_velocity(
double awr, double E, Direction u, double kT, uint64_t* seed);
void sample_fission_neutron(int i_nuclide, const Reaction& rx, double E_in,
SourceSite* site, uint64_t* seed);
void sample_fission_neutron(
int i_nuclide, const Reaction& rx, SourceSite* site, Particle& p);
//! handles all reactions with a single secondary neutron (other than fission),
//! i.e. level scattering, (n,np), (n,na), etc.

19
include/openmc/tallies/filter.h
View file

@ -157,5 +157,24 @@ extern vector<unique_ptr<Filter>> tally_filters;
//! Make sure index corresponds to a valid filter
int verify_filter(int32_t index);
//==============================================================================
// Filter implementation
//==============================================================================
template<typename T>
T* Filter::create(int32_t id)
{
static_assert(std::is_base_of<Filter, T>::value,
"Type specified is not derived from openmc::Filter");
// Create filter and add to filters vector
auto filter = make_unique<T>();
auto ptr_out = filter.get();
model::tally_filters.emplace_back(std::move(filter));
// Assign ID
model::tally_filters.back()->set_id(id);
return ptr_out;
}
} // namespace openmc
#endif // OPENMC_TALLIES_FILTER_H