Converted fission bank to SharedArray type.

include/openmc/bank.h

@@ -4,6 +4,7 @@
 #include <cstdint>
 #include <vector>
 
+#include "openmc/shared_array.h"
 #include "openmc/particle.h"
 #include "openmc/position.h"
 
@@ -17,9 +18,8 @@ namespace simulation {
 
 extern std::vector<Particle::Bank> source_bank;
 
-extern std::unique_ptr<Particle::Bank[]> fission_bank;
-extern int64_t fission_bank_length;
-extern int64_t fission_bank_max;
+extern SharedArray<Particle::Bank> fission_bank;
+
 extern std::vector<int64_t> progeny_per_particle;
 
 } // namespace simulation

include/openmc/shared_array.h

@@ -4,6 +4,9 @@
 //! \file shared_array.h
 //! \brief Shared array data structure
 
+#include<memory>
+
+
 namespace openmc {
 
 //==============================================================================

src/bank.cpp

@@ -17,15 +17,11 @@ namespace simulation {
 
 std::vector<Particle::Bank> source_bank;
 
-// The fission bank is allocated as a pointer, rather than a vector, as it will
+// 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 performing atomic incrementing captures on the fission_bank_length
-// variable. A vector is not appropriate, as use of push_back() and size()
-// functions would cause undefined or unintended behavior.
-std::unique_ptr<Particle::Bank[]> fission_bank;
-int64_t fission_bank_length {0};
-int64_t fission_bank_max;
+// added to it by using SharedArray's special thread_safe_append() function.
+SharedArray<Particle::Bank> fission_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
@@ -41,16 +37,13 @@ std::vector<int64_t> progeny_per_particle;
 void free_memory_bank()
 {
   simulation::source_bank.clear();
-  simulation::fission_bank.reset();
-  simulation::fission_bank_length = 0;
+  simulation::fission_bank.clear();
   simulation::progeny_per_particle.clear();
 }
 
 void init_fission_bank(int64_t max)
 {
-  simulation::fission_bank_max = max;
-  simulation::fission_bank = std::make_unique<Particle::Bank[]>(max);
-  simulation::fission_bank_length = 0;
+  simulation::fission_bank.reserve(max);
   simulation::progeny_per_particle.resize(simulation::work_per_rank);
 }
 
@@ -87,24 +80,24 @@ void sort_fission_bank()
   std::vector<Particle::Bank> sorted_bank_holder;
 
   // If there is not enough space, allocate a temporary vector and point to it
-  if (simulation::fission_bank_length > simulation::fission_bank_max / 2) {
-    sorted_bank_holder.resize(simulation::fission_bank_length);
+  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_length];
+    sorted_bank = &simulation::fission_bank[simulation::fission_bank.size()];
   }
 
   // Use parent and progeny indices to sort fission bank
-  for (int64_t i = 0; i < simulation::fission_bank_length; i++) {
+  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;
     sorted_bank[idx] = site;
   }
 
   // Copy sorted bank into the fission bank
-  std::copy(sorted_bank, sorted_bank + simulation::fission_bank_length,
-      simulation::fission_bank.get());
+  std::copy(sorted_bank, sorted_bank + simulation::fission_bank.size(),
+      simulation::fission_bank.data());
 }
 
 //==============================================================================
@@ -125,12 +118,12 @@ extern "C" int openmc_source_bank(void** ptr, int64_t* n)
 
 extern "C" int openmc_fission_bank(void** ptr, int64_t* n)
 {
-  if (simulation::fission_bank_length == 0) {
+  if (simulation::fission_bank.size() == 0) {
     set_errmsg("Fission bank has not been allocated.");
     return OPENMC_E_ALLOCATE;
   } else {
-    *ptr = simulation::fission_bank.get();
-    *n =   simulation::fission_bank_length;
+    *ptr = simulation::fission_bank.data();
+    *n =   simulation::fission_bank.size();
     return 0;
   }
 }

src/eigenvalue.cpp

@@ -83,21 +83,21 @@ void synchronize_bank()
 
 #ifdef OPENMC_MPI
   int64_t start = 0;
-  int64_t n_bank = simulation::fission_bank_length;
+  int64_t n_bank = simulation::fission_bank.size();
   MPI_Exscan(&n_bank, &start, 1, MPI_INT64_T, MPI_SUM, mpi::intracomm);
 
   // While we would expect the value of start on rank 0 to be 0, the MPI
   // standard says that the receive buffer on rank 0 is undefined and not
   // significant
   if (mpi::rank == 0) start = 0;
 
-  int64_t finish = start + simulation::fission_bank_length;
+  int64_t finish = start + simulation::fission_bank.size();
   int64_t total = finish;
   MPI_Bcast(&total, 1, MPI_INT64_T, mpi::n_procs - 1, mpi::intracomm);
 
 #else
   int64_t start  = 0;
-  int64_t finish = simulation::fission_bank_length;
+  int64_t finish = simulation::fission_bank.size();
   int64_t total  = finish;
 #endif
 
@@ -106,7 +106,7 @@ void synchronize_bank()
   // extra logic to treat this circumstance, we really want to ensure the user
   // runs enough particles to avoid this in the first place.
 
-  if (simulation::fission_bank_length == 0) {
+  if (simulation::fission_bank.size() == 0) {
     fatal_error("No fission sites banked on MPI rank " + std::to_string(mpi::rank));
   }
 
@@ -138,7 +138,7 @@ void synchronize_bank()
   int64_t index_temp = 0;
   std::vector<Particle::Bank> temp_sites(3*simulation::work_per_rank);
 
-  for (int64_t i = 0; i < simulation::fission_bank_length; i++ ) {
+  for (int64_t i = 0; i < simulation::fission_bank.size(); i++ ) {
     const auto& site = simulation::fission_bank[i];
 
     // If there are less than n_particles particles banked, automatically add
@@ -195,7 +195,7 @@ void synchronize_bank()
       // fission bank
       sites_needed = settings::n_particles - finish;
       for (int i = 0; i < sites_needed; ++i) {
-        int i_bank = simulation::fission_bank_length - sites_needed + i;
+        int i_bank = simulation::fission_bank.size() - sites_needed + i;
         temp_sites[index_temp] = simulation::fission_bank[i_bank];
         ++index_temp;
       }
@@ -506,7 +506,7 @@ void shannon_entropy()
   // Get source weight in each mesh bin
   bool sites_outside;
   xt::xtensor<double, 1> p = simulation::entropy_mesh->count_sites(
-    simulation::fission_bank.get(), simulation::fission_bank_length,
+    simulation::fission_bank.data(), simulation::fission_bank.size(),
     &sites_outside);
 
   // display warning message if there were sites outside entropy box

src/physics.cpp

@@ -16,7 +16,6 @@
 #include "openmc/secondary_uncorrelated.h"
 #include "openmc/search.h"
 #include "openmc/settings.h"
-#include "openmc/shared_array.h"
 #include "openmc/simulation.h"
 #include "openmc/string_utils.h"
 #include "openmc/thermal.h"
@@ -182,14 +181,10 @@ create_fission_sites(Particle* p, int i_nuclide, const Reaction* rx)
   for (int i = 0; i < nu; ++i) {
     Particle::Bank* site;
     if (use_fission_bank) {
-      int64_t idx;
-      #pragma omp atomic capture
-      idx = simulation::fission_bank_length++;
-      if (idx >= simulation::fission_bank_max) {
+      int64_t idx = simulation::fission_bank.thread_safe_append();
+      if (idx == -1) {
         warning("The shared fission bank is full. Additional fission sites created "
             "in this generation will not be banked.");
-        #pragma omp atomic write
-        simulation::fission_bank_length = simulation::fission_bank_max;
         skipped++;
         break;
       }

src/physics_mg.cpp

@@ -127,14 +127,10 @@ create_fission_sites(Particle* p)
   for (int i = 0; i < nu; ++i) {
     Particle::Bank* site;
     if (use_fission_bank) {
-      int64_t idx;
-      #pragma omp atomic capture
-      idx = simulation::fission_bank_length++;
-      if (idx >= simulation::fission_bank_max) {
+      int64_t idx = simulation::fission_bank.thread_safe_append();
+      if (idx == -1) {
         warning("The shared fission bank is full. Additional fission sites created "
             "in this generation will not be banked.");
-        #pragma omp atomic write
-        simulation::fission_bank_length = simulation::fission_bank_max;
         skipped++;
         break;
       }

src/simulation.cpp

@@ -375,7 +375,7 @@ void initialize_generation()
 {
   if (settings::run_mode == RunMode::EIGENVALUE) {
     // Clear out the fission bank
-    simulation::fission_bank_length = 0;
+    simulation::fission_bank.resize(0);
 
     // Count source sites if using uniform fission source weighting
     if (settings::ufs_on) ufs_count_sites();