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openmc-dev / openmc / 21009137102

14 Jan 2026 08:41PM UTC coverage: 82.044% (-0.01%) from 82.058%
21009137102

Pull #3727

github

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Merge ce04ba30c into 7861adf53
Pull Request #3727: Skip tests on documentation-only changes

17201 of 23887 branches covered (72.01%)

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88.13
/src/random_ray/linear_source_domain.cpp
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#include "openmc/random_ray/linear_source_domain.h"
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#include "openmc/cell.h"
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#include "openmc/geometry.h"
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#include "openmc/material.h"
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#include "openmc/message_passing.h"
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#include "openmc/mgxs_interface.h"
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#include "openmc/output.h"
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#include "openmc/plot.h"
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#include "openmc/random_ray/random_ray.h"
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#include "openmc/simulation.h"
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#include "openmc/tallies/filter.h"
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#include "openmc/tallies/tally.h"
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#include "openmc/tallies/tally_scoring.h"
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#include "openmc/timer.h"
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namespace openmc {
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//==============================================================================
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// LinearSourceDomain implementation
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//==============================================================================
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void LinearSourceDomain::batch_reset()
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{
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  FlatSourceDomain::batch_reset();
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#pragma omp parallel for
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  for (int64_t sr = 0; sr < n_source_regions(); sr++) {
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    source_regions_.centroid_iteration(sr) = {0.0, 0.0, 0.0};
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    source_regions_.mom_matrix(sr) = {0.0, 0.0, 0.0, 0.0, 0.0, 0.0};
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  }
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#pragma omp parallel for
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  for (int64_t se = 0; se < n_source_elements(); se++) {
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    source_regions_.flux_moments_new(se) = {0.0, 0.0, 0.0};
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  }
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}
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void LinearSourceDomain::update_single_neutron_source(SourceRegionHandle& srh)
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{
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  // Reset all source regions to zero (important for void regions)
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  for (int g = 0; g < negroups_; g++) {
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    srh.source(g) = 0.0;
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  }
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  // Add scattering + fission source
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  int material = srh.material();
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  double density_mult = srh.density_mult();
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  if (material != MATERIAL_VOID) {
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    double inverse_k_eff = 1.0 / k_eff_;
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    MomentMatrix invM = srh.mom_matrix().inverse();
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    for (int g_out = 0; g_out < negroups_; g_out++) {
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      double sigma_t = sigma_t_[material * negroups_ + g_out] * density_mult;
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      double scatter_flat = 0.0f;
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      double fission_flat = 0.0f;
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      MomentArray scatter_linear = {0.0, 0.0, 0.0};
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      MomentArray fission_linear = {0.0, 0.0, 0.0};
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      for (int g_in = 0; g_in < negroups_; g_in++) {
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        // Handles for the flat and linear components of the flux
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        double flux_flat = srh.scalar_flux_old(g_in);
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        MomentArray flux_linear = srh.flux_moments_old(g_in);
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        // Handles for cross sections
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        double sigma_s = sigma_s_[material * negroups_ * negroups_ +
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                                  g_out * negroups_ + g_in] *
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                         density_mult;
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        double nu_sigma_f =
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          nu_sigma_f_[material * negroups_ + g_in] * density_mult;
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        double chi = chi_[material * negroups_ + g_out];
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        // Compute source terms for flat and linear components of the flux
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        scatter_flat += sigma_s * flux_flat;
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        scatter_linear += sigma_s * flux_linear;
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        if (settings::create_fission_neutrons) {
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          fission_flat += nu_sigma_f * flux_flat * chi;
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          fission_linear += nu_sigma_f * flux_linear * chi;
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        }
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      }
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      // Compute the flat source term
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      srh.source(g_out) =
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        (scatter_flat + fission_flat * inverse_k_eff) / sigma_t;
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      // Compute the linear source terms. In the first 10 iterations when the
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      // centroids and spatial moments are not well known, we will leave the
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      // source gradients as zero so as to avoid causing any numerical
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      // instability. If a negative source is encountered, this region must be
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      // very small/noisy or have poorly developed spatial moments, so we zero
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      // the source gradients (effectively making this a flat source region
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      // temporarily), so as to improve stability.
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      if (simulation::current_batch > 10 && srh.source(g_out) >= 0.0) {
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        srh.source_gradients(g_out) =
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          invM * ((scatter_linear + fission_linear * inverse_k_eff) / sigma_t);
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      } else {
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        srh.source_gradients(g_out) = {0.0, 0.0, 0.0};
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      }
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    }
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  }
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  // Add external source if in fixed source mode
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  if (settings::run_mode == RunMode::FIXED_SOURCE) {
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    for (int g = 0; g < negroups_; g++) {
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      srh.source(g) += srh.external_source(g);
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    }
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  }
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}
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void LinearSourceDomain::normalize_scalar_flux_and_volumes(
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  double total_active_distance_per_iteration)
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{
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  double normalization_factor = 1.0 / total_active_distance_per_iteration;
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  double volume_normalization_factor =
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    1.0 / (total_active_distance_per_iteration * simulation::current_batch);
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// Normalize flux to total distance travelled by all rays this iteration
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#pragma omp parallel for
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  for (int64_t se = 0; se < n_source_elements(); se++) {
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    source_regions_.scalar_flux_new(se) *= normalization_factor;
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    source_regions_.flux_moments_new(se) *= normalization_factor;
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  }
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// Accumulate cell-wise ray length tallies collected this iteration, then
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// update the simulation-averaged cell-wise volume estimates
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#pragma omp parallel for
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  for (int64_t sr = 0; sr < n_source_regions(); sr++) {
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    source_regions_.centroid_t(sr) += source_regions_.centroid_iteration(sr);
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    source_regions_.mom_matrix_t(sr) += source_regions_.mom_matrix(sr);
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    source_regions_.volume_t(sr) += source_regions_.volume(sr);
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    source_regions_.volume_sq_t(sr) += source_regions_.volume_sq(sr);
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    source_regions_.volume_naive(sr) =
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      source_regions_.volume(sr) * normalization_factor;
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    source_regions_.volume(sr) =
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      source_regions_.volume_t(sr) * volume_normalization_factor;
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    source_regions_.volume_sq(sr) =
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      source_regions_.volume_sq_t(sr) / source_regions_.volume_t(sr);
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    if (source_regions_.volume_t(sr) > 0.0) {
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      double inv_volume = 1.0 / source_regions_.volume_t(sr);
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      source_regions_.centroid(sr) = source_regions_.centroid_t(sr);
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      source_regions_.centroid(sr) *= inv_volume;
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      source_regions_.mom_matrix(sr) = source_regions_.mom_matrix_t(sr);
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      source_regions_.mom_matrix(sr) *= inv_volume;
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    }
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  }
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}
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void LinearSourceDomain::set_flux_to_flux_plus_source(
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  int64_t sr, double volume, int g)
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{
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  int material = source_regions_.material(sr);
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  if (material == MATERIAL_VOID) {
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    FlatSourceDomain::set_flux_to_flux_plus_source(sr, volume, g);
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  } else {
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    source_regions_.scalar_flux_new(sr, g) /= volume;
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    source_regions_.scalar_flux_new(sr, g) += source_regions_.source(sr, g);
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  }
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  // If a source region is small, then the moments are likely noisy, so we zero
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  // them. This is reasonable, given that small regions can get by with a flat
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  // source approximation anyhow.
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  if (source_regions_.is_small(sr)) {
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    source_regions_.flux_moments_new(sr, g) = {0.0, 0.0, 0.0};
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  } else {
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    source_regions_.flux_moments_new(sr, g) *= (1.0 / volume);
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  }
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}
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void LinearSourceDomain::set_flux_to_old_flux(int64_t sr, int g)
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{
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  source_regions_.scalar_flux_new(sr, g) =
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    source_regions_.scalar_flux_old(sr, g);
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  source_regions_.flux_moments_new(sr, g) =
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    source_regions_.flux_moments_old(sr, g);
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}
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void LinearSourceDomain::accumulate_iteration_flux()
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{
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  // Accumulate scalar flux
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  FlatSourceDomain::accumulate_iteration_flux();
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  // Accumulate scalar flux moments
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#pragma omp parallel for
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  for (int64_t se = 0; se < n_source_elements(); se++) {
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    source_regions_.flux_moments_t(se) += source_regions_.flux_moments_new(se);
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  }
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}
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double LinearSourceDomain::evaluate_flux_at_point(
×
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  Position r, int64_t sr, int g) const
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{
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  double phi_flat = FlatSourceDomain::evaluate_flux_at_point(r, sr, g);
×
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  Position local_r = r - source_regions_.centroid(sr);
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  MomentArray phi_linear = source_regions_.flux_moments_t(sr, g);
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  phi_linear *= 1.0 / (settings::n_batches - settings::n_inactive);
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  MomentMatrix invM = source_regions_.mom_matrix(sr).inverse();
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  MomentArray phi_solved = invM * phi_linear;
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  return phi_flat + phi_solved.dot(local_r);
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}
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} // namespace openmc
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