crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-26 13:15:39 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

fixed one bug: I was initializing the shared fission vector before calculating work per rank, so probably size 0 or something, which caused all sorts of issues. Now we get an error at the end of the first power iteration, as it complains we have no fission sites on rank 0.

Browse source
This commit is contained in:
John Tramm 2019-11-19 22:34:42 +00:00
parent 8c1ebbd7fb
commit c5d2aa405e
1 changed files with 9 additions and 16 deletions
Download patch file Download diff file Expand all files Collapse all files

25
src/simulation.cpp
View file

@ -490,8 +490,6 @@ void check_energies(void)
n = calculate_fuel_xs_queue_length;
for( int i = 0; i < n; i++ )
{
Particle * p = particles + Q[i];
Particle p_true = *p;
if( !std::isfinite(particles[Q[i]].E_ ) )
{
std::cout << "NAN energy particle found at index xs FUEL " << Q[i] << std::endl;
@ -502,8 +500,6 @@ void check_energies(void)
n = calculate_nonfuel_xs_queue_length ;
for( int i = 0; i < n; i++ )
{
Particle * p = particles + Q[i];
Particle p_true = *p;
if( !std::isfinite(particles[Q[i]].E_ ) )
{
std::cout << "NAN energy particle found at index xs Non fuel " << Q[i] << std::endl;
@ -514,8 +510,6 @@ void check_energies(void)
n = advance_particle_queue_length ;
for( int i = 0; i < n; i++ )
{
Particle * p = particles + Q[i];
Particle p_true = *p;
if( !std::isfinite(particles[Q[i]].E_ ) )
{
std::cout << "NAN energy particle found at index advance particle " << Q[i] << std::endl;
@ -526,8 +520,6 @@ void check_energies(void)
n = surface_crossing_queue_length ;
for( int i = 0; i < n; i++ )
{
Particle * p = particles + Q[i];
Particle p_true = *p;
if( !std::isfinite(particles[Q[i]].E_ ) )
{
std::cout << "NAN energy particle found at index surface crossing " << Q[i] << std::endl;
@ -538,8 +530,6 @@ void check_energies(void)
n = collision_queue_length ;
for( int i = 0; i < n; i++ )
{
Particle * p = particles + Q[i];
Particle p_true = *p;
if( !std::isfinite(particles[Q[i]].E_ ) )
{
std::cout << "NAN energy particle found at index collision " << Q[i] << std::endl;
@ -676,15 +666,16 @@ int openmc_simulation_init()
// Skip if simulation has already been initialized
if (simulation::initialized) return 0;
// Determine how much work each process should do
calculate_work();
// We assume that the number of fission sites will be at most
// 10x the number of neutrons run on this rank
int shared_fission_bank_size = 10 * simulation::work_per_rank;
// Initializes the shared fission bank
init_shared_fission_bank(shared_fission_bank_size);
// Determine how much work each process should do
calculate_work();
// Allocate array for matching filter bins
#pragma omp parallel
{
@ -1082,9 +1073,11 @@ void finalize_generation()
//join_bank_from_threads();
// We need to move all the stuff from the shared_fission_bank into the real one.
//std::vector<Particle::Bank> shared_fission_bank_vector(shared_fission_bank, shared_fission_bank_length);
std::vector<Particle::Bank> shared_fission_bank_vector(shared_fission_bank, shared_fission_bank + shared_fission_bank_length);
simulation::fission_bank = shared_fission_bank_vector;
//std::vector<Particle::Bank> shared_fission_bank_vector(shared_fission_bank, shared_fission_bank + shared_fission_bank_length);
//simulation::fission_bank = shared_fission_bank_vector;
for( int i = 0; i < shared_fission_bank_length; i++ )
simulation::fission_bank.push_back(shared_fission_bank[i]);
shared_fission_bank_length = 0;
#endif
// Distribute fission bank across processors evenly