19929505944

Committed 04 Dec 2025 12:47PM UTC coverage: 82.063% (-0.005%) from 82.068%

Build # 19929505944

Build Type

Pull #3659

github

Committed by

web-flow

Commit Message

Merge 5d6b8bf87 into ad5a876be

Pull Request Pull Request #3659: Delayed neutron fraction by isotope with IFP method

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87.9

/src/random_ray/linear_source_domain.cpp

#include "openmc/random_ray/linear_source_domain.h"

#include "openmc/cell.h"
#include "openmc/geometry.h"
#include "openmc/material.h"
#include "openmc/message_passing.h"
#include "openmc/mgxs_interface.h"
#include "openmc/output.h"
#include "openmc/plot.h"
#include "openmc/random_ray/random_ray.h"
#include "openmc/simulation.h"
#include "openmc/tallies/filter.h"
#include "openmc/tallies/tally.h"
#include "openmc/tallies/tally_scoring.h"
#include "openmc/timer.h"

namespace openmc {

//==============================================================================
// LinearSourceDomain implementation
//==============================================================================

void LinearSourceDomain::batch_reset()
{
  FlatSourceDomain::batch_reset();
#pragma omp parallel for
  for (int64_t sr = 0; sr < n_source_regions(); sr++) {
    source_regions_.centroid_iteration(sr) = {0.0, 0.0, 0.0};
    source_regions_.mom_matrix(sr) = {0.0, 0.0, 0.0, 0.0, 0.0, 0.0};
  }
#pragma omp parallel for
  for (int64_t se = 0; se < n_source_elements(); se++) {
    source_regions_.flux_moments_new(se) = {0.0, 0.0, 0.0};
  }
}

void LinearSourceDomain::update_single_neutron_source(SourceRegionHandle& srh)
{
  // Reset all source regions to zero (important for void regions)
  for (int g = 0; g < negroups_; g++) {
    srh.source(g) = 0.0;
  }

  // Add scattering + fission source
  int material = srh.material();
  if (material != MATERIAL_VOID) {
    double inverse_k_eff = 1.0 / k_eff_;
    MomentMatrix invM = srh.mom_matrix().inverse();

    for (int g_out = 0; g_out < negroups_; g_out++) {
      double sigma_t = sigma_t_[material * negroups_ + g_out];

      double scatter_flat = 0.0f;
      double fission_flat = 0.0f;
      MomentArray scatter_linear = {0.0, 0.0, 0.0};
      MomentArray fission_linear = {0.0, 0.0, 0.0};

      for (int g_in = 0; g_in < negroups_; g_in++) {
        // Handles for the flat and linear components of the flux
        double flux_flat = srh.scalar_flux_old(g_in);
        MomentArray flux_linear = srh.flux_moments_old(g_in);

        // Handles for cross sections
        double sigma_s =
          sigma_s_[material * negroups_ * negroups_ + g_out * negroups_ + g_in];
        double nu_sigma_f = nu_sigma_f_[material * negroups_ + g_in];
        double chi = chi_[material * negroups_ + g_out];

        // Compute source terms for flat and linear components of the flux
        scatter_flat += sigma_s * flux_flat;
        scatter_linear += sigma_s * flux_linear;
        if (settings::create_fission_neutrons) {
          fission_flat += nu_sigma_f * flux_flat * chi;
          fission_linear += nu_sigma_f * flux_linear * chi;
        }
      }

      // Compute the flat source term
      srh.source(g_out) =
        (scatter_flat + fission_flat * inverse_k_eff) / sigma_t;

      // Compute the linear source terms. In the first 10 iterations when the
      // centroids and spatial moments are not well known, we will leave the
      // source gradients as zero so as to avoid causing any numerical
      // instability. If a negative source is encountered, this region must be
      // very small/noisy or have poorly developed spatial moments, so we zero
      // the source gradients (effectively making this a flat source region
      // temporarily), so as to improve stability.
      if (simulation::current_batch > 10 && srh.source(g_out) >= 0.0) {
        srh.source_gradients(g_out) =
          invM * ((scatter_linear + fission_linear * inverse_k_eff) / sigma_t);
      } else {
        srh.source_gradients(g_out) = {0.0, 0.0, 0.0};
      }
    }
  }

  // Add external source if in fixed source mode
  if (settings::run_mode == RunMode::FIXED_SOURCE) {
    for (int g = 0; g < negroups_; g++) {
      srh.source(g) += srh.external_source(g);
    }
  }
}

void LinearSourceDomain::normalize_scalar_flux_and_volumes(
  double total_active_distance_per_iteration)
{
  double normalization_factor = 1.0 / total_active_distance_per_iteration;
  double volume_normalization_factor =
    1.0 / (total_active_distance_per_iteration * simulation::current_batch);

// Normalize flux to total distance travelled by all rays this iteration
#pragma omp parallel for
  for (int64_t se = 0; se < n_source_elements(); se++) {
    source_regions_.scalar_flux_new(se) *= normalization_factor;
    source_regions_.flux_moments_new(se) *= normalization_factor;
  }

// Accumulate cell-wise ray length tallies collected this iteration, then
// update the simulation-averaged cell-wise volume estimates
#pragma omp parallel for
  for (int64_t sr = 0; sr < n_source_regions(); sr++) {
    source_regions_.centroid_t(sr) += source_regions_.centroid_iteration(sr);
    source_regions_.mom_matrix_t(sr) += source_regions_.mom_matrix(sr);
    source_regions_.volume_t(sr) += source_regions_.volume(sr);
    source_regions_.volume_sq_t(sr) += source_regions_.volume_sq(sr);
    source_regions_.volume_naive(sr) =
      source_regions_.volume(sr) * normalization_factor;
    source_regions_.volume(sr) =
      source_regions_.volume_t(sr) * volume_normalization_factor;
    source_regions_.volume_sq(sr) =
      source_regions_.volume_sq_t(sr) / source_regions_.volume_t(sr);
    if (source_regions_.volume_t(sr) > 0.0) {
      double inv_volume = 1.0 / source_regions_.volume_t(sr);
      source_regions_.centroid(sr) = source_regions_.centroid_t(sr);
      source_regions_.centroid(sr) *= inv_volume;
      source_regions_.mom_matrix(sr) = source_regions_.mom_matrix_t(sr);
      source_regions_.mom_matrix(sr) *= inv_volume;
    }
  }
}

void LinearSourceDomain::set_flux_to_flux_plus_source(
  int64_t sr, double volume, int g)
{
  int material = source_regions_.material(sr);
  if (material == MATERIAL_VOID) {
    FlatSourceDomain::set_flux_to_flux_plus_source(sr, volume, g);
  } else {
    source_regions_.scalar_flux_new(sr, g) /= volume;
    source_regions_.scalar_flux_new(sr, g) += source_regions_.source(sr, g);
  }
  // If a source region is small, then the moments are likely noisy, so we zero
  // them. This is reasonable, given that small regions can get by with a flat
  // source approximation anyhow.
  if (source_regions_.is_small(sr)) {
    source_regions_.flux_moments_new(sr, g) = {0.0, 0.0, 0.0};
  } else {
    source_regions_.flux_moments_new(sr, g) *= (1.0 / volume);
  }
}

void LinearSourceDomain::set_flux_to_old_flux(int64_t sr, int g)
{
  source_regions_.scalar_flux_new(sr, g) =
    source_regions_.scalar_flux_old(sr, g);
  source_regions_.flux_moments_new(sr, g) =
    source_regions_.flux_moments_old(sr, g);
}

void LinearSourceDomain::accumulate_iteration_flux()
{
  // Accumulate scalar flux
  FlatSourceDomain::accumulate_iteration_flux();

  // Accumulate scalar flux moments
#pragma omp parallel for
  for (int64_t se = 0; se < n_source_elements(); se++) {
    source_regions_.flux_moments_t(se) += source_regions_.flux_moments_new(se);
  }
}

double LinearSourceDomain::evaluate_flux_at_point(
  Position r, int64_t sr, int g) const
{
  double phi_flat = FlatSourceDomain::evaluate_flux_at_point(r, sr, g);

  Position local_r = r - source_regions_.centroid(sr);
  MomentArray phi_linear = source_regions_.flux_moments_t(sr, g);
  phi_linear *= 1.0 / (settings::n_batches - settings::n_inactive);

  MomentMatrix invM = source_regions_.mom_matrix(sr).inverse();
  MomentArray phi_solved = invM * phi_linear;

  return phi_flat + phi_solved.dot(local_r);
}

} // namespace openmc

1	#include "openmc/random_ray/linear_source_domain.h"
2
3	#include "openmc/cell.h"
4	#include "openmc/geometry.h"
5	#include "openmc/material.h"
6	#include "openmc/message_passing.h"
7	#include "openmc/mgxs_interface.h"
8	#include "openmc/output.h"
9	#include "openmc/plot.h"
10	#include "openmc/random_ray/random_ray.h"
11	#include "openmc/simulation.h"
12	#include "openmc/tallies/filter.h"
13	#include "openmc/tallies/tally.h"
14	#include "openmc/tallies/tally_scoring.h"
15	#include "openmc/timer.h"
16
17	namespace openmc {
18
19	//==============================================================================
20	// LinearSourceDomain implementation
21	//==============================================================================
22
23	void LinearSourceDomain::batch_reset()	6,875✔
24	{
25	FlatSourceDomain::batch_reset();	6,875✔
26	#pragma omp parallel for	3,750✔
27	for (int64_t sr = 0; sr < n_source_regions(); sr++) {	13,100,550✔
28	source_regions_.centroid_iteration(sr) = {0.0, 0.0, 0.0};	13,097,425✔
29	source_regions_.mom_matrix(sr) = {0.0, 0.0, 0.0, 0.0, 0.0, 0.0};	13,097,425✔
30	}
31	#pragma omp parallel for	3,750✔
32	for (int64_t se = 0; se < n_source_elements(); se++) {	15,061,470✔
33	source_regions_.flux_moments_new(se) = {0.0, 0.0, 0.0};	15,058,345✔
34	}
35	}	6,875✔
36
37	void LinearSourceDomain::update_single_neutron_source(SourceRegionHandle& srh)	29,635,397✔
38	{
39	// Reset all source regions to zero (important for void regions)
40	for (int g = 0; g < negroups_; g++) {	63,653,194✔
41	srh.source(g) = 0.0;	34,017,797✔
42	}
43
44	// Add scattering + fission source
45	int material = srh.material();	29,635,397✔
46	if (material != MATERIAL_VOID) {	29,635,397✔
47	double inverse_k_eff = 1.0 / k_eff_;	29,195,397✔
48	MomentMatrix invM = srh.mom_matrix().inverse();	29,195,397✔
49
50	for (int g_out = 0; g_out < negroups_; g_out++) {	62,773,194✔
51	double sigma_t = sigma_t_[material * negroups_ + g_out];	33,577,797✔
52
53	double scatter_flat = 0.0f;	33,577,797✔
54	double fission_flat = 0.0f;	33,577,797✔
55	MomentArray scatter_linear = {0.0, 0.0, 0.0};	33,577,797✔
56	MomentArray fission_linear = {0.0, 0.0, 0.0};	33,577,797✔
57
58	for (int g_in = 0; g_in < negroups_; g_in++) {	109,325,634✔
59	// Handles for the flat and linear components of the flux
60	double flux_flat = srh.scalar_flux_old(g_in);	75,747,837✔
61	MomentArray flux_linear = srh.flux_moments_old(g_in);	75,747,837✔
62
63	// Handles for cross sections
64	double sigma_s =
65	sigma_s_[material * negroups_ * negroups_ + g_out * negroups_ + g_in];	75,747,837✔
66	double nu_sigma_f = nu_sigma_f_[material * negroups_ + g_in];	75,747,837✔
67	double chi = chi_[material * negroups_ + g_out];	75,747,837✔
68
69	// Compute source terms for flat and linear components of the flux
70	scatter_flat += sigma_s * flux_flat;	75,747,837✔
71	scatter_linear += sigma_s * flux_linear;	75,747,837✔
72	if (settings::create_fission_neutrons) {	75,747,837!
73	fission_flat += nu_sigma_f * flux_flat * chi;	75,747,837✔
74	fission_linear += nu_sigma_f * flux_linear * chi;	75,747,837✔
75	}
76	}
77
78	// Compute the flat source term
79	srh.source(g_out) =	67,155,594✔
80	(scatter_flat + fission_flat * inverse_k_eff) / sigma_t;	33,577,797✔
81
82	// Compute the linear source terms. In the first 10 iterations when the
83	// centroids and spatial moments are not well known, we will leave the
84	// source gradients as zero so as to avoid causing any numerical
85	// instability. If a negative source is encountered, this region must be
86	// very small/noisy or have poorly developed spatial moments, so we zero
87	// the source gradients (effectively making this a flat source region
88	// temporarily), so as to improve stability.
89	if (simulation::current_batch > 10 && srh.source(g_out) >= 0.0) {	33,577,797✔
90	srh.source_gradients(g_out) =	20,559,022✔
91	invM * ((scatter_linear + fission_linear * inverse_k_eff) / sigma_t);	41,118,044✔
92	} else {
93	srh.source_gradients(g_out) = {0.0, 0.0, 0.0};	13,018,775✔
94	}
95	}
96	}
97
98	// Add external source if in fixed source mode
99	if (settings::run_mode == RunMode::FIXED_SOURCE) {	29,635,397✔
100	for (int g = 0; g < negroups_; g++) {	61,688,594✔
101	srh.source(g) += srh.external_source(g);	32,279,797✔
102	}
103	}
104	}	29,635,397✔
105
106	void LinearSourceDomain::normalize_scalar_flux_and_volumes(	6,875✔
107	double total_active_distance_per_iteration)
108	{
109	double normalization_factor = 1.0 / total_active_distance_per_iteration;	6,875✔
110	double volume_normalization_factor =	6,875✔
111	1.0 / (total_active_distance_per_iteration * simulation::current_batch);	6,875✔
112
113	// Normalize flux to total distance travelled by all rays this iteration
114	#pragma omp parallel for	3,750✔
115	for (int64_t se = 0; se < n_source_elements(); se++) {	15,450,690✔
116	source_regions_.scalar_flux_new(se) *= normalization_factor;	15,447,565✔
117	source_regions_.flux_moments_new(se) *= normalization_factor;	15,447,565✔
118	}
119
120	// Accumulate cell-wise ray length tallies collected this iteration, then
121	// update the simulation-averaged cell-wise volume estimates
122	#pragma omp parallel for	3,750✔
123	for (int64_t sr = 0; sr < n_source_regions(); sr++) {	13,458,690✔
124	source_regions_.centroid_t(sr) += source_regions_.centroid_iteration(sr);	13,455,565✔
125	source_regions_.mom_matrix_t(sr) += source_regions_.mom_matrix(sr);	13,455,565✔
126	source_regions_.volume_t(sr) += source_regions_.volume(sr);	13,455,565✔
127	source_regions_.volume_sq_t(sr) += source_regions_.volume_sq(sr);	13,455,565✔
128	source_regions_.volume_naive(sr) =	26,911,130✔
129	source_regions_.volume(sr) * normalization_factor;	13,455,565✔
130	source_regions_.volume(sr) =	26,911,130✔
131	source_regions_.volume_t(sr) * volume_normalization_factor;	13,455,565✔
132	source_regions_.volume_sq(sr) =	26,911,130✔
133	source_regions_.volume_sq_t(sr) / source_regions_.volume_t(sr);	13,455,565✔
134	if (source_regions_.volume_t(sr) > 0.0) {	13,455,565✔
135	double inv_volume = 1.0 / source_regions_.volume_t(sr);	13,455,560✔
136	source_regions_.centroid(sr) = source_regions_.centroid_t(sr);	13,455,560✔
137	source_regions_.centroid(sr) *= inv_volume;	13,455,560✔
138	source_regions_.mom_matrix(sr) = source_regions_.mom_matrix_t(sr);	13,455,560✔
139	source_regions_.mom_matrix(sr) *= inv_volume;	13,455,560✔
140	}
141	}
142	}	6,875✔
143
144	void LinearSourceDomain::set_flux_to_flux_plus_source(	31,089,949✔
145	int64_t sr, double volume, int g)
146	{
147	int material = source_regions_.material(sr);	31,089,949✔
148	if (material == MATERIAL_VOID) {	31,089,949✔
149	FlatSourceDomain::set_flux_to_flux_plus_source(sr, volume, g);	440,000✔
150	} else {
151	source_regions_.scalar_flux_new(sr, g) /= volume;	30,649,949✔
152	source_regions_.scalar_flux_new(sr, g) += source_regions_.source(sr, g);	30,649,949✔
153	}
154	// If a source region is small, then the moments are likely noisy, so we zero
155	// them. This is reasonable, given that small regions can get by with a flat
156	// source approximation anyhow.
157	if (source_regions_.is_small(sr)) {	31,089,949✔
158	source_regions_.flux_moments_new(sr, g) = {0.0, 0.0, 0.0};	3,158,254✔
159	} else {
160	source_regions_.flux_moments_new(sr, g) *= (1.0 / volume);	27,931,695✔
161	}
162	}	31,089,949✔
163
164	void LinearSourceDomain::set_flux_to_old_flux(int64_t sr, int g)	1,364✔
165	{
166	source_regions_.scalar_flux_new(sr, g) =	2,728✔
167	source_regions_.scalar_flux_old(sr, g);	1,364✔
168	source_regions_.flux_moments_new(sr, g) =	2,728✔
169	source_regions_.flux_moments_old(sr, g);	1,364✔
170	}	1,364✔
171
172	void LinearSourceDomain::accumulate_iteration_flux()	2,860✔
173	{
174	// Accumulate scalar flux
175	FlatSourceDomain::accumulate_iteration_flux();	2,860✔
176
177	// Accumulate scalar flux moments
178	#pragma omp parallel for	1,560✔
179	for (int64_t se = 0; se < n_source_elements(); se++) {	6,586,800✔
180	source_regions_.flux_moments_t(se) += source_regions_.flux_moments_new(se);	6,585,500✔
181	}
182	}	2,860✔
183
UNCOV 184	double LinearSourceDomain::evaluate_flux_at_point(	×
185	Position r, int64_t sr, int g) const
186	{
187	double phi_flat = FlatSourceDomain::evaluate_flux_at_point(r, sr, g);	×
188
189	Position local_r = r - source_regions_.centroid(sr);	×
UNCOV 190	MomentArray phi_linear = source_regions_.flux_moments_t(sr, g);	×
191	phi_linear *= 1.0 / (settings::n_batches - settings::n_inactive);	×
192
UNCOV 193	MomentMatrix invM = source_regions_.mom_matrix(sr).inverse();	×
194	MomentArray phi_solved = invM * phi_linear;	×
195
UNCOV 196	return phi_flat + phi_solved.dot(local_r);	×
197	}
198
199	} // namespace openmc

openmc-dev / openmc / 19929505944

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