19102841639

Committed 05 Nov 2025 01:01PM UTC coverage: 82.019% (-3.1%) from 85.155%

Build # 19102841639

Build Type

Pull #3252

github

Committed by

web-flow

Commit Message

Merge 3c71decac into bd76fc056

Pull Request Pull Request #3252: Adding vtkhdf option to write vtk data

Run Details

16722 of 23233 branches covered (71.98%)

Branch coverage included in aggregate %.

61 of 66 new or added lines in 1 file covered. (92.42%)

3177 existing lines in 103 files now uncovered.

54247 of 63294 relevant lines covered (85.71%)

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72.16

/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;

// 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::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	// The fission bank is allocated as a SharedArray, rather than a vector, as it
24	// will be shared by all threads in the simulation. It will be allocated to a
25	// fixed maximum capacity in the init_fission_bank() function. Then, Elements
26	// will be added to it by using SharedArray's special thread_safe_append()
27	// function.
28	SharedArray<SourceSite> fission_bank;
29
30	vector<vector<int>> ifp_source_delayed_group_bank;
31
32	vector<vector<double>> ifp_source_lifetime_bank;
33
34	vector<vector<int>> ifp_fission_delayed_group_bank;
35
36	vector<vector<double>> ifp_fission_lifetime_bank;
37
38	// Each entry in this vector corresponds to the number of progeny produced
39	// this generation for the particle located at that index. This vector is
40	// used to efficiently sort the fission bank after each iteration.
41	vector<int64_t> progeny_per_particle;
42
43	} // namespace simulation
44
45	//==============================================================================
46	// Non-member functions
47	//==============================================================================
48
49	void free_memory_bank()	8,104✔
50	{
51	simulation::source_bank.clear();	8,104✔
52	simulation::surf_source_bank.clear();	8,104✔
53	simulation::fission_bank.clear();	8,104✔
54	simulation::progeny_per_particle.clear();	8,104✔
55	simulation::ifp_source_delayed_group_bank.clear();	8,104✔
56	simulation::ifp_source_lifetime_bank.clear();	8,104✔
57	simulation::ifp_fission_delayed_group_bank.clear();	8,104✔
58	simulation::ifp_fission_lifetime_bank.clear();	8,104✔
59	}	8,104✔
60
61	void init_fission_bank(int64_t max)	3,756✔
62	{
63	simulation::fission_bank.reserve(max);	3,756✔
64	simulation::progeny_per_particle.resize(simulation::work_per_rank);	3,756✔
65	}	3,756✔
66
67	// Performs an O(n) sort on the fission bank, by leveraging
68	// the parent_id and progeny_id fields of banked particles. See the following
69	// paper for more details:
70	// "Reproducibility and Monte Carlo Eigenvalue Calculations," F.B. Brown and
71	// T.M. Sutton, 1992 ANS Annual Meeting, Transactions of the American Nuclear
72	// Society, Volume 65, Page 235.
73	void sort_fission_bank()	83,347✔
74	{
75	// Ensure we don't read off the end of the array if we ran with 0 particles
76	if (simulation::progeny_per_particle.size() == 0) {	83,347!
77	return;	×
78	}
79
80	// Perform exclusive scan summation to determine starting indices in fission
81	// bank for each parent particle id
82	std::exclusive_scan(simulation::progeny_per_particle.begin(),	83,347✔
83	simulation::progeny_per_particle.end(),
84	simulation::progeny_per_particle.begin(), 0);
85
86	// We need a scratch vector to make permutation of the fission bank into
87	// sorted order easy. Under normal usage conditions, the fission bank is
88	// over provisioned, so we can use that as scratch space.
89	SourceSite* sorted_bank;
90	vector<SourceSite> sorted_bank_holder;	83,347✔
91	vector<vector<int>> sorted_ifp_delayed_group_bank;	83,347✔
92	vector<vector<double>> sorted_ifp_lifetime_bank;	83,347✔
93
94	// If there is not enough space, allocate a temporary vector and point to it
95	if (simulation::fission_bank.size() >	83,347✔
96	simulation::fission_bank.capacity() / 2) {	83,347✔
97	sorted_bank_holder.resize(simulation::fission_bank.size());	850✔
98	sorted_bank = sorted_bank_holder.data();	850✔
99	} else { // otherwise, point sorted_bank to unused portion of the fission bank
100	sorted_bank = &simulation::fission_bank[simulation::fission_bank.size()];	82,497✔
101	}
102
103	if (settings::ifp_on) {	83,347✔
104	allocate_temporary_vector_ifp(	1,520✔
105	sorted_ifp_delayed_group_bank, sorted_ifp_lifetime_bank);
106	}
107
108	// Use parent and progeny indices to sort fission bank
109	for (int64_t i = 0; i < simulation::fission_bank.size(); i++) {	140,311,903✔
110	const auto& site = simulation::fission_bank[i];	140,228,556✔
111	int64_t offset = site.parent_id - 1 - simulation::work_index[mpi::rank];	140,228,556✔
112	int64_t idx = simulation::progeny_per_particle[offset] + site.progeny_id;	140,228,556✔
113	if (idx >= simulation::fission_bank.size()) {	140,228,556!
UNCOV 114	fatal_error("Mismatch detected between sum of all particle progeny and "	×
115	"shared fission bank size.");
116	}
117	sorted_bank[idx] = site;	140,228,556✔
118	if (settings::ifp_on) {	140,228,556✔
119	copy_ifp_data_from_fission_banks(	1,352,626✔
120	i, sorted_ifp_delayed_group_bank[idx], sorted_ifp_lifetime_bank[idx]);	1,352,626✔
121	}
122	}
123
124	// Copy sorted bank into the fission bank
125	std::copy(sorted_bank, sorted_bank + simulation::fission_bank.size(),	83,347✔
126	simulation::fission_bank.data());
127	if (settings::ifp_on) {	83,347✔
128	copy_ifp_data_to_fission_banks(	1,520✔
129	sorted_ifp_delayed_group_bank.data(), sorted_ifp_lifetime_bank.data());	1,520✔
130	}
131	}	83,347✔
132
133	//==============================================================================
134	// C API
135	//==============================================================================
136
137	extern "C" int openmc_source_bank(void** ptr, int64_t* n)	12✔
138	{
139	if (!ptr \|\| !n) {	12!
UNCOV 140	set_errmsg("Received null pointer.");	×
UNCOV 141	return OPENMC_E_INVALID_ARGUMENT;	×
142	}
143
144	if (simulation::source_bank.size() == 0) {	12!
UNCOV 145	set_errmsg("Source bank has not been allocated.");	×
UNCOV 146	return OPENMC_E_ALLOCATE;	×
147	} else {
148	*ptr = simulation::source_bank.data();	12✔
149	*n = simulation::source_bank.size();	12✔
150	return 0;	12✔
151	}
152	}
153
UNCOV 154	extern "C" int openmc_fission_bank(void** ptr, int64_t* n)	×
155	{
UNCOV 156	if (!ptr \|\| !n) {	×
UNCOV 157	set_errmsg("Received null pointer.");	×
UNCOV 158	return OPENMC_E_INVALID_ARGUMENT;	×
159	}
160
161	if (simulation::fission_bank.size() == 0) {	×
UNCOV 162	set_errmsg("Fission bank has not been allocated.");	×
163	return OPENMC_E_ALLOCATE;	×
164	} else {
165	*ptr = simulation::fission_bank.data();	×
UNCOV 166	*n = simulation::fission_bank.size();	×
UNCOV 167	return 0;	×
168	}
169	}
170
171	} // namespace openmc

openmc-dev / openmc / 19102841639

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