mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-26 13:15:39 -04:00
fixed bug by partially removing multigroup support
This commit is contained in:
parent
54698ec7da
commit
6333392936
1 changed files with 5 additions and 10 deletions
|
|
@ -186,21 +186,16 @@ void process_calculate_xs_events(std::vector<Particle*>& queue)
|
|||
for (auto& p : queue) {
|
||||
// Calculate microscopic and macroscopic cross sections
|
||||
if (p->material_ != MATERIAL_VOID) {
|
||||
if (settings::run_CE) {
|
||||
// Only works for CE, no MG support
|
||||
//if (settings::run_CE) {
|
||||
// If the material is the same as the last material and the
|
||||
// temperature hasn't changed, we don't need to lookup cross
|
||||
// sections again.
|
||||
model::materials[p->material_]->calculate_xs(*p);
|
||||
} else {
|
||||
// Get the MG data
|
||||
calculate_xs_c(p->material_, p->g_, p->sqrtkT_, p->u_local(),
|
||||
p->macro_xs_.total, p->macro_xs_.absorption, p->macro_xs_.nu_fission);
|
||||
|
||||
// Finally, update the particle group while we have already checked
|
||||
// for if multi-group
|
||||
p->g_last_ = p->g_;
|
||||
}
|
||||
} else {
|
||||
//else {
|
||||
//}
|
||||
else {
|
||||
p->macro_xs_.total = 0.0;
|
||||
p->macro_xs_.absorption = 0.0;
|
||||
p->macro_xs_.fission = 0.0;
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue