19851502091

Committed 02 Dec 2025 08:05AM UTC coverage: 82.016% (+0.1%) from 81.872%

Build # 19851502091

Build Type

Pull #3413

github

Committed by

web-flow

Commit Message

Merge d7a168452 into ef22558f4

Pull Request Pull Request #3413: More interpolation types in Tabular.

Run Details

16946 of 23531 branches covered (72.02%)

Branch coverage included in aggregate %.

68 of 107 new or added lines in 3 files covered. (63.55%)

1391 existing lines in 31 files now uncovered.

54939 of 64116 relevant lines covered (85.69%)

42115001.1 hits per line

Source File
Press 'n' to go to next uncovered line, 'b' for previous

72.45

/src/bank.cpp

#include "openmc/bank.h"
#include "openmc/capi.h"
#include "openmc/error.h"
#include "openmc/ifp.h"
#include "openmc/message_passing.h"
#include "openmc/simulation.h"
#include "openmc/vector.h"

#include <cstdint>

namespace openmc {

//==============================================================================
// Global variables
//==============================================================================

namespace simulation {

vector<SourceSite> source_bank;

SharedArray<SourceSite> surf_source_bank;

SharedArray<CollisionTrackSite> collision_track_bank;

// The fission bank is allocated as a SharedArray, rather than a vector, as it
// will be shared by all threads in the simulation. It will be allocated to a
// fixed maximum capacity in the init_fission_bank() function. Then, Elements
// will be added to it by using SharedArray's special thread_safe_append()
// function.
SharedArray<SourceSite> fission_bank;

vector<vector<int>> ifp_source_delayed_group_bank;

vector<vector<double>> ifp_source_lifetime_bank;

vector<vector<int>> ifp_fission_delayed_group_bank;

vector<vector<double>> ifp_fission_lifetime_bank;

// Each entry in this vector corresponds to the number of progeny produced
// this generation for the particle located at that index. This vector is
// used to efficiently sort the fission bank after each iteration.
vector<int64_t> progeny_per_particle;

} // namespace simulation

//==============================================================================
// Non-member functions
//==============================================================================

void free_memory_bank()
{
  simulation::source_bank.clear();
  simulation::surf_source_bank.clear();
  simulation::collision_track_bank.clear();
  simulation::fission_bank.clear();
  simulation::progeny_per_particle.clear();
  simulation::ifp_source_delayed_group_bank.clear();
  simulation::ifp_source_lifetime_bank.clear();
  simulation::ifp_fission_delayed_group_bank.clear();
  simulation::ifp_fission_lifetime_bank.clear();
}

void init_fission_bank(int64_t max)
{
  simulation::fission_bank.reserve(max);
  simulation::progeny_per_particle.resize(simulation::work_per_rank);
}

// Performs an O(n) sort on the fission bank, by leveraging
// the parent_id and progeny_id fields of banked particles. See the following
// paper for more details:
// "Reproducibility and Monte Carlo Eigenvalue Calculations," F.B. Brown and
// T.M. Sutton, 1992 ANS Annual Meeting, Transactions of the American Nuclear
// Society, Volume 65, Page 235.
void sort_fission_bank()
{
  // Ensure we don't read off the end of the array if we ran with 0 particles
  if (simulation::progeny_per_particle.size() == 0) {
    return;
  }

  // Perform exclusive scan summation to determine starting indices in fission
  // bank for each parent particle id
  std::exclusive_scan(simulation::progeny_per_particle.begin(),
    simulation::progeny_per_particle.end(),
    simulation::progeny_per_particle.begin(), 0);

  // We need a scratch vector to make permutation of the fission bank into
  // sorted order easy. Under normal usage conditions, the fission bank is
  // over provisioned, so we can use that as scratch space.
  SourceSite* sorted_bank;
  vector<SourceSite> sorted_bank_holder;
  vector<vector<int>> sorted_ifp_delayed_group_bank;
  vector<vector<double>> sorted_ifp_lifetime_bank;

  // If there is not enough space, allocate a temporary vector and point to it
  if (simulation::fission_bank.size() >
      simulation::fission_bank.capacity() / 2) {
    sorted_bank_holder.resize(simulation::fission_bank.size());
    sorted_bank = sorted_bank_holder.data();
  } else { // otherwise, point sorted_bank to unused portion of the fission bank
    sorted_bank = &simulation::fission_bank[simulation::fission_bank.size()];
  }

  if (settings::ifp_on) {
    allocate_temporary_vector_ifp(
      sorted_ifp_delayed_group_bank, sorted_ifp_lifetime_bank);
  }

  // Use parent and progeny indices to sort fission bank
  for (int64_t i = 0; i < simulation::fission_bank.size(); i++) {
    const auto& site = simulation::fission_bank[i];
    int64_t offset = site.parent_id - 1 - simulation::work_index[mpi::rank];
    int64_t idx = simulation::progeny_per_particle[offset] + site.progeny_id;
    if (idx >= simulation::fission_bank.size()) {
      fatal_error("Mismatch detected between sum of all particle progeny and "
                  "shared fission bank size.");
    }
    sorted_bank[idx] = site;
    if (settings::ifp_on) {
      copy_ifp_data_from_fission_banks(
        i, sorted_ifp_delayed_group_bank[idx], sorted_ifp_lifetime_bank[idx]);
    }
  }

  // Copy sorted bank into the fission bank
  std::copy(sorted_bank, sorted_bank + simulation::fission_bank.size(),
    simulation::fission_bank.data());
  if (settings::ifp_on) {
    copy_ifp_data_to_fission_banks(
      sorted_ifp_delayed_group_bank.data(), sorted_ifp_lifetime_bank.data());
  }
}

//==============================================================================
// C API
//==============================================================================

extern "C" int openmc_source_bank(void** ptr, int64_t* n)
{
  if (!ptr || !n) {
    set_errmsg("Received null pointer.");
    return OPENMC_E_INVALID_ARGUMENT;
  }

  if (simulation::source_bank.size() == 0) {
    set_errmsg("Source bank has not been allocated.");
    return OPENMC_E_ALLOCATE;
  } else {
    *ptr = simulation::source_bank.data();
    *n = simulation::source_bank.size();
    return 0;
  }
}

extern "C" int openmc_fission_bank(void** ptr, int64_t* n)
{
  if (!ptr || !n) {
    set_errmsg("Received null pointer.");
    return OPENMC_E_INVALID_ARGUMENT;
  }

  if (simulation::fission_bank.size() == 0) {
    set_errmsg("Fission bank has not been allocated.");
    return OPENMC_E_ALLOCATE;
  } else {
    *ptr = simulation::fission_bank.data();
    *n = simulation::fission_bank.size();
    return 0;
  }
}

} // namespace openmc

1	#include "openmc/bank.h"
2	#include "openmc/capi.h"
3	#include "openmc/error.h"
4	#include "openmc/ifp.h"
5	#include "openmc/message_passing.h"
6	#include "openmc/simulation.h"
7	#include "openmc/vector.h"
8
9	#include <cstdint>
10
11	namespace openmc {
12
13	//==============================================================================
14	// Global variables
15	//==============================================================================
16
17	namespace simulation {
18
19	vector<SourceSite> source_bank;
20
21	SharedArray<SourceSite> surf_source_bank;
22
23	SharedArray<CollisionTrackSite> collision_track_bank;
24
25	// The fission bank is allocated as a SharedArray, rather than a vector, as it
26	// will be shared by all threads in the simulation. It will be allocated to a
27	// fixed maximum capacity in the init_fission_bank() function. Then, Elements
28	// will be added to it by using SharedArray's special thread_safe_append()
29	// function.
30	SharedArray<SourceSite> fission_bank;
31
32	vector<vector<int>> ifp_source_delayed_group_bank;
33
34	vector<vector<double>> ifp_source_lifetime_bank;
35
36	vector<vector<int>> ifp_fission_delayed_group_bank;
37
38	vector<vector<double>> ifp_fission_lifetime_bank;
39
40	// Each entry in this vector corresponds to the number of progeny produced
41	// this generation for the particle located at that index. This vector is
42	// used to efficiently sort the fission bank after each iteration.
43	vector<int64_t> progeny_per_particle;
44
45	} // namespace simulation
46
47	//==============================================================================
48	// Non-member functions
49	//==============================================================================
50
51	void free_memory_bank()	7,490✔
52	{
53	simulation::source_bank.clear();	7,490✔
54	simulation::surf_source_bank.clear();	7,490✔
55	simulation::collision_track_bank.clear();	7,490✔
56	simulation::fission_bank.clear();	7,490✔
57	simulation::progeny_per_particle.clear();	7,490✔
58	simulation::ifp_source_delayed_group_bank.clear();	7,490✔
59	simulation::ifp_source_lifetime_bank.clear();	7,490✔
60	simulation::ifp_fission_delayed_group_bank.clear();	7,490✔
61	simulation::ifp_fission_lifetime_bank.clear();	7,490✔
62	}	7,490✔
63
64	void init_fission_bank(int64_t max)	3,845✔
65	{
66	simulation::fission_bank.reserve(max);	3,845✔
67	simulation::progeny_per_particle.resize(simulation::work_per_rank);	3,845✔
68	}	3,845✔
69
70	// Performs an O(n) sort on the fission bank, by leveraging
71	// the parent_id and progeny_id fields of banked particles. See the following
72	// paper for more details:
73	// "Reproducibility and Monte Carlo Eigenvalue Calculations," F.B. Brown and
74	// T.M. Sutton, 1992 ANS Annual Meeting, Transactions of the American Nuclear
75	// Society, Volume 65, Page 235.
76	void sort_fission_bank()	83,193✔
77	{
78	// Ensure we don't read off the end of the array if we ran with 0 particles
79	if (simulation::progeny_per_particle.size() == 0) {	83,193!
UNCOV 80	return;	×
81	}
82
83	// Perform exclusive scan summation to determine starting indices in fission
84	// bank for each parent particle id
85	std::exclusive_scan(simulation::progeny_per_particle.begin(),	83,193✔
86	simulation::progeny_per_particle.end(),
87	simulation::progeny_per_particle.begin(), 0);
88
89	// We need a scratch vector to make permutation of the fission bank into
90	// sorted order easy. Under normal usage conditions, the fission bank is
91	// over provisioned, so we can use that as scratch space.
92	SourceSite* sorted_bank;
93	vector<SourceSite> sorted_bank_holder;	83,193✔
94	vector<vector<int>> sorted_ifp_delayed_group_bank;	83,193✔
95	vector<vector<double>> sorted_ifp_lifetime_bank;	83,193✔
96
97	// If there is not enough space, allocate a temporary vector and point to it
98	if (simulation::fission_bank.size() >	83,193✔
99	simulation::fission_bank.capacity() / 2) {	83,193✔
100	sorted_bank_holder.resize(simulation::fission_bank.size());	884✔
101	sorted_bank = sorted_bank_holder.data();	884✔
102	} else { // otherwise, point sorted_bank to unused portion of the fission bank
103	sorted_bank = &simulation::fission_bank[simulation::fission_bank.size()];	82,309✔
104	}
105
106	if (settings::ifp_on) {	83,193✔
107	allocate_temporary_vector_ifp(	1,520✔
108	sorted_ifp_delayed_group_bank, sorted_ifp_lifetime_bank);
109	}
110
111	// Use parent and progeny indices to sort fission bank
112	for (int64_t i = 0; i < simulation::fission_bank.size(); i++) {	139,782,244✔
113	const auto& site = simulation::fission_bank[i];	139,699,051✔
114	int64_t offset = site.parent_id - 1 - simulation::work_index[mpi::rank];	139,699,051✔
115	int64_t idx = simulation::progeny_per_particle[offset] + site.progeny_id;	139,699,051✔
116	if (idx >= simulation::fission_bank.size()) {	139,699,051!
UNCOV 117	fatal_error("Mismatch detected between sum of all particle progeny and "	×
118	"shared fission bank size.");
119	}
120	sorted_bank[idx] = site;	139,699,051✔
121	if (settings::ifp_on) {	139,699,051✔
122	copy_ifp_data_from_fission_banks(	1,352,626✔
123	i, sorted_ifp_delayed_group_bank[idx], sorted_ifp_lifetime_bank[idx]);	1,352,626✔
124	}
125	}
126
127	// Copy sorted bank into the fission bank
128	std::copy(sorted_bank, sorted_bank + simulation::fission_bank.size(),	83,193✔
129	simulation::fission_bank.data());
130	if (settings::ifp_on) {	83,193✔
131	copy_ifp_data_to_fission_banks(	1,520✔
132	sorted_ifp_delayed_group_bank.data(), sorted_ifp_lifetime_bank.data());	1,520✔
133	}
134	}	83,193✔
135
136	//==============================================================================
137	// C API
138	//==============================================================================
139
140	extern "C" int openmc_source_bank(void** ptr, int64_t* n)	11✔
141	{
142	if (!ptr \|\| !n) {	11!
UNCOV 143	set_errmsg("Received null pointer.");	×
UNCOV 144	return OPENMC_E_INVALID_ARGUMENT;	×
145	}
146
147	if (simulation::source_bank.size() == 0) {	11!
UNCOV 148	set_errmsg("Source bank has not been allocated.");	×
UNCOV 149	return OPENMC_E_ALLOCATE;	×
150	} else {
151	*ptr = simulation::source_bank.data();	11✔
152	*n = simulation::source_bank.size();	11✔
153	return 0;	11✔
154	}
155	}
156
157	extern "C" int openmc_fission_bank(void** ptr, int64_t* n)	×
158	{
UNCOV 159	if (!ptr \|\| !n) {	×
UNCOV 160	set_errmsg("Received null pointer.");	×
161	return OPENMC_E_INVALID_ARGUMENT;	×
162	}
163
UNCOV 164	if (simulation::fission_bank.size() == 0) {	×
165	set_errmsg("Fission bank has not been allocated.");	×
166	return OPENMC_E_ALLOCATE;	×
167	} else {
UNCOV 168	*ptr = simulation::fission_bank.data();	×
UNCOV 169	*n = simulation::fission_bank.size();	×
UNCOV 170	return 0;	×
171	}
172	}
173
174	} // namespace openmc

openmc-dev / openmc / 19851502091

Source File Press 'n' to go to next uncovered line, 'b' for previous

Source File
Press 'n' to go to next uncovered line, 'b' for previous