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

Remove most of remaining components of Material type on Fortran side

Browse source
This commit is contained in:
Paul Romano 2019-01-25 16:00:00 -06:00
parent 223a15b52f
commit 63aa3bf106
11 changed files with 225 additions and 510 deletions
Download patch file Download diff file Expand all files Collapse all files

9
src/simulation.cpp
View file

@ -5,6 +5,7 @@
#include "openmc/container_util.h"
#include "openmc/eigenvalue.h"
#include "openmc/error.h"
#include "openmc/material.h"
#include "openmc/message_passing.h"
#include "openmc/nuclide.h"
#include "openmc/output.h"
@ -91,6 +92,11 @@ int openmc_simulation_init()
// Allocate tally results arrays if they're not allocated yet
allocate_tally_results();
// Set up material nuclide index mapping
for (auto& mat : model::materials) {
mat->init_nuclide_index();
}
// Call Fortran initialization
simulation_init_f();
set_micro_xs();
@ -144,6 +150,9 @@ int openmc_simulation_finalize()
}
// Deallocate Fortran variables, set tallies to inactive
for (auto& mat : model::materials) {
mat->mat_nuclide_index_.clear();
}
simulation_finalize_f();
// Increment total number of generations