crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 06:05:58 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Move sample_neutron_reaction and create_fission_sites to C++

Browse source
This commit is contained in:
Paul Romano 2018-11-17 15:43:10 -06:00
parent 2942790afc
commit 8859714592
7 changed files with 260 additions and 310 deletions
Download patch file Download diff file Expand all files Collapse all files

2
src/simulation.cpp
View file

@ -6,6 +6,7 @@
#include "openmc/eigenvalue.h"
#include "openmc/error.h"
#include "openmc/message_passing.h"
#include "openmc/nuclide.h"
#include "openmc/output.h"
#include "openmc/particle.h"
#include "openmc/random_lcg.h"
@ -100,6 +101,7 @@ int openmc_simulation_init()
// Call Fortran initialization
simulation_init_f();
set_micro_xs();
// Reset global variables -- this is done before loading state point (as that
// will potentially populate k_generation and entropy)