Differentiate materials in DAGMC universes

include/openmc/capi.h

@@ -29,6 +29,8 @@ int openmc_cell_set_temperature(
   int32_t index, double T, const int32_t* instance, bool set_contained = false);
 int openmc_cell_set_translation(int32_t index, const double xyz[]);
 int openmc_cell_set_rotation(int32_t index, const double rot[], size_t rot_len);
+int openmc_get_dagmc_cell_ids(int32_t univ_id, int32_t* ids, size_t* n);
+int openmc_dagmc_universe_get_num_cells(int32_t univ_id, size_t* n);
 int openmc_energy_filter_get_bins(
   int32_t index, const double** energies, size_t* n);
 int openmc_energy_filter_set_bins(

include/openmc/cell.h

@@ -320,7 +320,6 @@ class Cell {
   int32_t universe_;        //!< Universe # this cell is in
   int32_t fill_;            //!< Universe # filling this cell
   int32_t n_instances_ {0}; //!< Number of instances of this cell
-  GeometryType geom_type_;  //!< Geometric representation type (CSG, DAGMC)
 
   //! \brief Index corresponding to this cell in distribcell arrays
   int distribcell_index_ {C_NONE};
@@ -350,6 +349,13 @@ class Cell {
   vector<double> rotation_;
 
   vector<int32_t> offset_; //!< Distribcell offset table
+
+  // Accessors
+  const GeometryType& geom_type() const { return geom_type_; }
+  GeometryType& geom_type() { return geom_type_; }
+
+private:
+  GeometryType geom_type_; //!< Geometric representation type (CSG, DAGMC)
 };
 
 struct CellInstanceItem {

include/openmc/dagmc.h

@@ -184,6 +184,7 @@ class DAGUniverse : public Universe {
                              //!< generate new material IDs for the universe
   bool has_graveyard_; //!< Indicates if the DAGMC geometry has a "graveyard"
                        //!< volume
+  std::map<std::string, vector<std::string>> instance_material_overrides;
 };
 
 //==============================================================================

openmc/__init__.py

@@ -15,6 +15,7 @@
 from openmc.weight_windows import *
 from openmc.surface import *
 from openmc.universe import *
+from openmc.dagmc import *
 from openmc.source import *
 from openmc.settings import *
 from openmc.lattice import *

openmc/cell.py

@@ -780,3 +780,5 @@ def from_xml_element(cls, elem, surfaces, materials, get_universe):
         univ_id = int(get_text(elem, 'universe', 0))
         get_universe(univ_id).add_cell(c)
         return c
+
+