crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 22:26:08 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Evaluate neutron xs once per reaction in sample_photon_product

Browse source
This commit is contained in:
Paul Romano 2018-11-28 08:35:52 -06:00
parent c44bea2556
commit 5f90fe3a9d
1 changed files with 5 additions and 3 deletions
Download patch file Download diff file Expand all files Collapse all files

8
src/physics.cpp
View file

@ -551,12 +551,14 @@ void sample_photon_product(int i_nuclide, double E, int* i_rx, int* i_product)
// if energy is below threshold for this reaction, skip it
if (i_grid < threshold) continue;
// Evaluate neutron cross section
double xs = ((1.0 - f) * rx->xs_[i_temp-1].value[i_grid - threshold]
+ f*(rx->xs_[i_temp-1].value[i_grid - threshold + 1]));
for (int j = 0; j < rx->products_.size(); ++j) {
if (rx->products_[j].particle_ == ParticleType::photon) {
// add to cumulative probability
double yield = (*rx->products_[j].yield_)(E);
prob += ((1.0 - f) * rx->xs_[i_temp-1].value[i_grid - threshold]
+ f*(rx->xs_[i_temp-1].value[i_grid - threshold + 1])) * yield;
prob += (*rx->products_[j].yield_)(E) * xs;
*i_rx = i;
*i_product = j;