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60 lines
1.7 KiB
C++
60 lines
1.7 KiB
C++
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#include "openmc/capi.h"
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#include "openmc/cell.h"
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#include "openmc/geometry.h"
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#include "openmc/summary.h"
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#include "openmc/tallies/filter.h"
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#include "openmc/tallies/filter_cell.h"
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#include "openmc/tallies/tally.h"
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using namespace openmc;
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int main(int argc, char** argv) {
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openmc_init(argc, argv, nullptr);
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// create a new cell filter
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auto cell_filter = Filter::create<CellFilter>();
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// add all cells to the cell filter
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std::vector<int32_t> cell_indices;
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for (auto& entry : openmc::model::cell_map) {
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cell_indices.push_back(entry.second);
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}
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// sort to make sure the cell bins appear in the same
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// order as the test relying on the openmc exe
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std::sort(cell_indices.begin(), cell_indices.end());
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cell_filter->set_cells(cell_indices);
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// create a new tally
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auto tally = Tally::create();
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std::vector<Filter*> filters = {cell_filter};
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tally->set_filters(filters);
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tally->set_scores({"flux"});
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// set the temperature of the cell containing
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// the lattice
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auto& root_univ = openmc::model::universes[openmc::model::root_universe];
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auto& lattice_cell = openmc::model::cells[root_univ->cells_[0]];
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lattice_cell->set_temperature(300, 1, true);
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// check that material-filled cells return no contained cells
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for (auto& cell : openmc::model::cells) {
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if (cell->type_ == Fill::MATERIAL) {
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auto contained_cells = cell->get_contained_cells();
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assert(contained_cells.empty());
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}
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}
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// the summary file will be used to check that
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// temperatures were set correctly so clear
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// error output can be provided
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#ifdef OPENMC_MPI
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if (openmc::mpi::master) openmc::write_summary();
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#else
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openmc::write_summary();
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#endif
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openmc_run();
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openmc_finalize();
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return 0;
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}
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