#include "openmc/particle_data.h"

#include "openmc/cell.h"

#include "openmc/geometry.h"

#include "openmc/material.h"

#include "openmc/nuclide.h"

#include "openmc/photon.h"

#include "openmc/settings.h"

#include "openmc/tallies/derivative.h"

#include "openmc/tallies/filter.h"

#include "openmc/tallies/tally.h"

namespace openmc {

void LocalCoord::rotate(const vector<double>& rotation)

{

r = r.rotate(rotation);

u = u.rotate(rotation);

rotated = true;

}

void LocalCoord::reset()

{

cell = C_NONE;

universe = C_NONE;

lattice = C_NONE;

lattice_i[0] = 0;

lattice_i[1] = 0;

lattice_i[2] = 0;

rotated = false;

}

ParticleData::ParticleData()

{

// Create and clear coordinate levels

coord_.resize(model::n_coord_levels);

cell_last_.resize(model::n_coord_levels);

clear();

zero_delayed_bank();

// Every particle starts with no accumulated flux derivative. Note that in

// event mode, we construct the particle once up front, so have to run this

// even if the current batch is inactive.

if (!model::active_tallies.empty() || settings::event_based) {

flux_derivs_.resize(model::tally_derivs.size());

zero_flux_derivs();

}

// Allocate space for tally filter matches

filter_matches_.resize(model::tally_filters.size());

// Create microscopic cross section caches

neutron_xs_.resize(data::nuclides.size());

photon_xs_.resize(data::elements.size());

}

TrackState ParticleData::get_track_state() const

{

TrackState state;

state.r = this->r();

state.u = this->u();

state.E = this->E();

state.time = this->time();

state.wgt = this->wgt();

state.cell_id = model::cells[this->lowest_coord().cell]->id_;

state.cell_instance = this->cell_instance();

if (this->material() != MATERIAL_VOID) {

state.material_id = model::materials[material()]->id_;

}

return state;

}

} // namespace openmc