/**
* @brief Computes the total source (fission, scattering, fixed) in each FSR.
* @details This method computes the total source in each FSR based on
* this iteration's current approximation to the scalar flux.
*/
void VectorizedSolver::computeFSRSources() {
#pragma omp parallel default(none)
{
int tid;
Material* material;
FP_PRECISION* sigma_t;
FP_PRECISION* sigma_s;
FP_PRECISION* fiss_mat;
FP_PRECISION scatter_source, fission_source;
int size = _num_groups * sizeof(FP_PRECISION);
FP_PRECISION* fission_sources =
(FP_PRECISION*)MM_MALLOC(size, VEC_ALIGNMENT);
FP_PRECISION* scatter_sources =
(FP_PRECISION*)MM_MALLOC(size, VEC_ALIGNMENT);
/* For all FSRs, find the source */
#pragma omp for schedule(guided)
for (int r=0; r < _num_FSRs; r++) {
tid = omp_get_thread_num();
material = _FSR_materials[r];
sigma_t = material->getSigmaT();
sigma_s = material->getSigmaS();
fiss_mat = material->getFissionMatrix();
/* Compute scatter + fission source for group G */
for (int G=0; G < _num_groups; G++) {
for (int v=0; v < _num_vector_lengths; v++) {
#pragma simd vectorlength(VEC_LENGTH)
for (int g=v*VEC_LENGTH; g < (v+1)*VEC_LENGTH; g++) {
scatter_sources[g] = sigma_s[G*_num_groups+g] * _scalar_flux(r,g);
fission_sources[g] = fiss_mat[G*_num_groups+g] * _scalar_flux(r,g);
}
}
#ifdef SINGLE
scatter_source=cblas_sasum(_num_groups, scatter_sources, 1);
fission_source=cblas_sasum(_num_groups, fission_sources, 1);
#else
scatter_source=cblas_dasum(_num_groups, scatter_sources, 1);
fission_source=cblas_dasum(_num_groups, fission_sources, 1);
#endif
fission_source /= _k_eff;
/* Compute total (scatter+fission+fixed) reduced source */
_reduced_sources(r,G) = _fixed_sources(r,G);
_reduced_sources(r,G) += scatter_source + fission_source;
_reduced_sources(r,G) *= ONE_OVER_FOUR_PI / sigma_t[G];
}
}
MM_FREE(fission_sources);
MM_FREE(scatter_sources);
}
}
/**
* @brief Add the source term contribution in the transport equation to
* the FSR scalar flux
*/
void VectorizedSolver::addSourceToScalarFlux() {
FP_PRECISION volume;
FP_PRECISION* sigma_t;
/* Add in source term and normalize flux to volume for each FSR */
/* Loop over FSRs, energy groups */
#pragma omp parallel for private(volume, sigma_t) schedule(guided)
for (int r=0; r < _num_FSRs; r++) {
volume = _FSR_volumes[r];
sigma_t = _FSR_materials[r]->getSigmaT();
/* Loop over each energy group vector length */
for (int v=0; v < _num_vector_lengths; v++) {
/* Loop over energy groups within this vector */
#pragma simd vectorlength(VEC_LENGTH)
for (int e=v*VEC_LENGTH; e < (v+1)*VEC_LENGTH; e++)
_scalar_flux(r,e) *= 0.5;
/* Loop over energy groups within this vector */
#pragma simd vectorlength(VEC_LENGTH)
for (int e=v*VEC_LENGTH; e < (v+1)*VEC_LENGTH; e++)
_scalar_flux(r,e) = _scalar_flux(r,e) / (sigma_t[e] * volume);
/* Loop over energy groups within this vector */
#pragma simd vectorlength(VEC_LENGTH)
for (int e=v*VEC_LENGTH; e < (v+1)*VEC_LENGTH; e++)
_scalar_flux(r,e) += FOUR_PI * _reduced_sources(r,e);
}
}
return;
}
/**
* @brief Computes the contribution to the FSR scalar flux from a segment.
* @details This method integrates the angular flux for a Track segment across
* energy groups and polar angles, and tallies it into the FSR scalar
* flux, and updates the Track's angular flux.
* @param curr_segment a pointer to the Track segment of interest
* @param azim_index a pointer to the azimuthal angle index for this segment
* @param track_flux a pointer to the Track's angular flux
* @param fsr_flux a pointer to the temporary FSR flux buffer
*/
void VectorizedSolver::tallyScalarFlux(segment* curr_segment,
int azim_index,
FP_PRECISION* track_flux,
FP_PRECISION* fsr_flux) {
int tid = omp_get_thread_num();
int fsr_id = curr_segment->_region_id;
FP_PRECISION* delta_psi = &_delta_psi[tid*_num_groups];
FP_PRECISION* exponentials = &_thread_exponentials[tid*_polar_times_groups];
computeExponentials(curr_segment, exponentials);
/* Set the FSR scalar flux buffer to zero */
memset(fsr_flux, 0.0, _num_groups * sizeof(FP_PRECISION));
/* Tally the flux contribution from segment to FSR's scalar flux */
/* Loop over polar angles */
for (int p=0; p < _num_polar; p++) {
/* Loop over each energy group vector length */
for (int v=0; v < _num_vector_lengths; v++) {
/* Loop over energy groups within this vector */
#pragma simd vectorlength(VEC_LENGTH)
for (int e=v*VEC_LENGTH; e < (v+1)*VEC_LENGTH; e++)
delta_psi[e] = track_flux(p,e) - _reduced_sources(fsr_id,e);
/* Loop over energy groups within this vector */
#pragma simd vectorlength(VEC_LENGTH)
for (int e=v*VEC_LENGTH; e < (v+1)*VEC_LENGTH; e++)
delta_psi[e] *= exponentials(p,e);
/* Loop over energy groups within this vector */
#pragma simd vectorlength(VEC_LENGTH)
for (int e=v*VEC_LENGTH; e < (v+1)*VEC_LENGTH; e++)
fsr_flux[e] += delta_psi[e] * _polar_weights(azim_index,p);
/* Loop over energy groups within this vector */
#pragma simd vectorlength(VEC_LENGTH)
for (int e=v*VEC_LENGTH; e < (v+1)*VEC_LENGTH; e++)
track_flux(p,e) -= delta_psi[e];
}
}
/* Atomically increment the FSR scalar flux from the temporary array */
omp_set_lock(&_FSR_locks[fsr_id]);
{
#ifdef SINGLE
vsAdd(_num_groups, &_scalar_flux(fsr_id,0), fsr_flux,
&_scalar_flux(fsr_id,0));
#else
vdAdd(_num_groups, &_scalar_flux(fsr_id,0), fsr_flux,
&_scalar_flux(fsr_id,0));
#endif
}
omp_unset_lock(&_FSR_locks[fsr_id]);
}
/**
* @brief Add the source term contribution in the transport equation to
* the FSR scalar flux.
*/
void CPUSolver::addSourceToScalarFlux() {
FP_PRECISION volume;
FP_PRECISION* sigma_t;
/* Add in source term and normalize flux to volume for each FSR */
/* Loop over FSRs, energy groups */
#pragma omp parallel for private(volume, sigma_t) schedule(guided)
for (int r=0; r < _num_FSRs; r++) {
volume = _FSR_volumes[r];
sigma_t = _FSR_materials[r]->getSigmaT();
for (int e=0; e < _num_groups; e++) {
_scalar_flux(r,e) *= 0.5;
_scalar_flux(r,e) = FOUR_PI * _reduced_sources(r,e) +
(_scalar_flux(r,e) / (sigma_t[e] * volume));
}
}
return;
}
/**
* @brief Computes the contribution to the FSR scalar flux from a Track segment.
* @details This method integrates the angular flux for a Track segment across
* energy groups and polar angles, and tallies it into the FSR
* scalar flux, and updates the Track's angular flux.
* @param curr_segment a pointer to the Track segment of interest
* @param azim_index a pointer to the azimuthal angle index for this segment
* @param track_flux a pointer to the Track's angular flux
* @param fsr_flux a pointer to the temporary FSR flux buffer
* @param fwd
*/
void CPUSolver::scalarFluxTally(segment* curr_segment,
int azim_index,
FP_PRECISION* track_flux,
FP_PRECISION* fsr_flux,
bool fwd){
int tid = omp_get_thread_num();
int fsr_id = curr_segment->_region_id;
FP_PRECISION length = curr_segment->_length;
FP_PRECISION* sigma_t = curr_segment->_material->getSigmaT();
/* The change in angular flux along this Track segment in the FSR */
FP_PRECISION delta_psi;
FP_PRECISION exponential;
/* Set the FSR scalar flux buffer to zero */
memset(fsr_flux, 0.0, _num_groups * sizeof(FP_PRECISION));
/* Loop over energy groups */
for (int e=0; e < _num_groups; e++) {
/* Loop over polar angles */
for (int p=0; p < _num_polar; p++){
exponential = computeExponential(sigma_t[e], length, p);
delta_psi = (track_flux(p,e)-_reduced_sources(fsr_id,e))*exponential;
fsr_flux[e] += delta_psi * _polar_weights(azim_index,p);
track_flux(p,e) -= delta_psi;
}
}
if (_cmfd != NULL && _cmfd->isFluxUpdateOn()){
if (curr_segment->_cmfd_surface_fwd != -1 && fwd){
int pe = 0;
/* Atomically increment the Cmfd Mesh surface current from the
* temporary array using mutual exclusion locks */
omp_set_lock(&_cmfd_surface_locks[curr_segment->_cmfd_surface_fwd]);
/* Loop over energy groups */
for (int e = 0; e < _num_groups; e++) {
/* Loop over polar angles */
for (int p = 0; p < _num_polar; p++){
/* Increment current (polar and azimuthal weighted flux, group) */
_surface_currents(curr_segment->_cmfd_surface_fwd,e) +=
track_flux(p,e)*_polar_weights(azim_index,p)/2.0;
pe++;
}
}
/* Release Cmfd Mesh surface mutual exclusion lock */
omp_unset_lock(&_cmfd_surface_locks[curr_segment->_cmfd_surface_fwd]);
}
else if (curr_segment->_cmfd_surface_bwd != -1 && !fwd){
int pe = 0;
/* Atomically increment the Cmfd Mesh surface current from the
* temporary array using mutual exclusion locks */
omp_set_lock(&_cmfd_surface_locks[curr_segment->_cmfd_surface_bwd]);
/* Loop over energy groups */
for (int e = 0; e < _num_groups; e++) {
/* Loop over polar angles */
for (int p = 0; p < _num_polar; p++){
/* Increment current (polar and azimuthal weighted flux, group) */
_surface_currents(curr_segment->_cmfd_surface_bwd,e) +=
track_flux(p,e)*_polar_weights(azim_index,p)/2.0;
pe++;
}
}
/* Release Cmfd Mesh surface mutual exclusion lock */
omp_unset_lock(&_cmfd_surface_locks[curr_segment->_cmfd_surface_bwd]);
}
}
/* Atomically increment the FSR scalar flux from the temporary array */
omp_set_lock(&_FSR_locks[fsr_id]);
{
for (int e=0; e < _num_groups; e++)
_scalar_flux(fsr_id,e) += fsr_flux[e];
}
omp_unset_lock(&_FSR_locks[fsr_id]);
return;
}
/**
* @brief Computes the total source (fission and scattering) in each FSR.
* @details This method computes the total source in each FSR based on
* this iteration's current approximation to the scalar flux. A
* residual for the source with respect to the source compute on
* the previous iteration is computed and returned. The residual
* is determined as follows:
* \f$ res = \sqrt{\frac{\displaystyle\sum \displaystyle\sum
* \left(\frac{Q^i - Q^{i-1}}{Q^i}\right)^2}{\# FSRs}} \f$
*
* @return the residual between this source and the previous source
*/
FP_PRECISION CPUSolver::computeFSRSources() {
int tid;
Material* material;
FP_PRECISION scatter_source;
FP_PRECISION fission_source;
FP_PRECISION fsr_fission_source;
FP_PRECISION* nu_sigma_f;
FP_PRECISION* sigma_s;
FP_PRECISION* sigma_t;
FP_PRECISION* chi;
FP_PRECISION source_residual = 0.0;
FP_PRECISION inverse_k_eff = 1.0 / _k_eff;
/* For all FSRs, find the source */
#pragma omp parallel for private(tid, material, nu_sigma_f, chi, \
sigma_s, sigma_t, fission_source, scatter_source, fsr_fission_source) \
schedule(guided)
for (int r=0; r < _num_FSRs; r++) {
tid = omp_get_thread_num();
material = _FSR_materials[r];
nu_sigma_f = material->getNuSigmaF();
chi = material->getChi();
sigma_s = material->getSigmaS();
sigma_t = material->getSigmaT();
/* Initialize the source residual to zero */
_source_residuals[r] = 0.;
fsr_fission_source = 0.0;
/* Compute fission source for each group */
if (material->isFissionable()) {
for (int e=0; e < _num_groups; e++)
_fission_sources(r,e) = _scalar_flux(r,e) * nu_sigma_f[e];
fission_source = pairwise_sum<FP_PRECISION>(&_fission_sources(r,0),
_num_groups);
fission_source *= inverse_k_eff;
}
else
fission_source = 0.0;
/* Compute total scattering source for group G */
for (int G=0; G < _num_groups; G++) {
scatter_source = 0;
for (int g=0; g < _num_groups; g++)
_scatter_sources(tid,g) = material->getSigmaSByGroupInline(g,G)
* _scalar_flux(r,g);
scatter_source=pairwise_sum<FP_PRECISION>(&_scatter_sources(tid,0),
_num_groups);
/* Set the fission source for FSR r in group G */
fsr_fission_source += fission_source * chi[G];
/* Set the reduced source for FSR r in group G */
_reduced_sources(r,G) = (fission_source * chi[G] + scatter_source) *
ONE_OVER_FOUR_PI / sigma_t[G];
}
/* Compute the norm of residual of the source in the FSR */
if (fsr_fission_source > 0.0)
_source_residuals[r] = pow((fsr_fission_source - _old_fission_sources[r])
/ fsr_fission_source, 2);
/* Update the old source */
_old_fission_sources[r] = fsr_fission_source;
}
/* Sum up the residuals from each FSR */
source_residual = pairwise_sum<FP_PRECISION>(_source_residuals, _num_FSRs);
source_residual = sqrt(source_residual \
/ (_num_fissionable_FSRs * _num_groups));
return source_residual;
}
