5. Summary File FormatΒΆ
The current revision of the summary file format is 1.
/filetype (char[])
String indicating the type of file.
/revision (int)
Revision of the summary file format. Any time a change is made in the format, this integer is incremented.
/version_major (int)
Major version number for OpenMC
/version_minor (int)
Minor version number for OpenMC
/version_release (int)
Release version number for OpenMC
/date_and_time (char[])
Date and time the summary was written.
/n_procs (int)
Number of MPI processes used.
/n_particles (int8_t)
Number of particles used per generation.
/n_batches (int)
Number of batches to simulate.
/n_inactive (int)
Number of inactive batches. Only present if /run_mode is set to ‘k-eigenvalue’.
/n_active (int)
Number of active batches. Only present if /run_mode is set to ‘k-eigenvalue’.
/gen_per_batch (int)
Number of generations per batch. Only present if /run_mode is set to ‘k-eigenvalue’.
/geometry/n_cells (int)
Number of cells in the problem.
/geometry/n_surfaces (int)
Number of surfaces in the problem.
/geometry/n_universes (int)
Number of unique universes in the problem.
/geometry/n_lattices (int)
Number of lattices in the problem.
/geometry/cells/cell <uid>/index (int)
Index in cells array used internally in OpenMC.
/geometry/cells/cell <uid>/name (char[])
Name of the cell.
/geometry/cells/cell <uid>/universe (int)
Universe assigned to the cell. If none is specified, the default universe (0) is assigned.
/geometry/cells/cell <uid>/fill_type (char[])
Type of fill for the cell. Can be ‘normal’, ‘universe’, or ‘lattice’.
/geometry/cells/cell <uid>/material (int or int[])
Unique ID of the material(s) assigned to the cell. This dataset is present only if fill_type is set to ‘normal’. The value ‘-1’ signifies void material. The data is an array if the cell uses distributed materials, otherwise it is a scalar.
/geometry/cells/cell <uid>/temperature (double[])
Temperature of the cell in Kelvin.
/geometry/cells/cell <uid>/offset (int[])
Offsets used for distribcell tally filter. This dataset is present only if fill_type is set to ‘universe’.
/geometry/cells/cell <uid>/translation (double[3])
Translation applied to the fill universe. This dataset is present only if fill_type is set to ‘universe’.
/geometry/cells/cell <uid>/rotation (double[3])
Angles in degrees about the x-, y-, and z-axes for which the fill universe should be rotated. This dataset is present only if fill_type is set to ‘universe’.
/geometry/cells/cell <uid>/lattice (int)
Unique ID of the lattice which fills the cell. Only present if fill_type is set to ‘lattice’.
/geometry/cells/cell <uid>/region (char[])
Region specification for the cell.
/geometry/cells/cell <uid>/distribcell_index (int)
Index of this cell in distribcell filter arrays.
/geometry/surfaces/surface <uid>/index (int)
Index in surfaces array used internally in OpenMC.
/geometry/surfaces/surface <uid>/name (char[])
Name of the surface.
/geometry/surfaces/surface <uid>/type (char[])
Type of the surface. Can be ‘x-plane’, ‘y-plane’, ‘z-plane’, ‘plane’, ‘x-cylinder’, ‘y-cylinder’, ‘sphere’, ‘x-cone’, ‘y-cone’, ‘z-cone’, or ‘quadric’.
/geometry/surfaces/surface <uid>/coefficients (double[])
Array of coefficients that define the surface. See <surface> Element for what coefficients are defined for each surface type.
/geometry/surfaces/surface <uid>/boundary_condition (char[])
Boundary condition applied to the surface. Can be ‘transmission’, ‘vacuum’, ‘reflective’, or ‘periodic’.
/geometry/universes/universe <uid>/index (int)
Index in the universes array used internally in OpenMC.
/geometry/universes/universe <uid>/cells (int[])
Array of unique IDs of cells that appear in the universe.
/geometry/lattices/lattice <uid>/index (int)
Index in the lattices array used internally in OpenMC.
/geometry/lattices/lattice <uid>/name (char[])
Name of the lattice.
/geometry/lattices/lattice <uid>/type (char[])
Type of the lattice, either ‘rectangular’ or ‘hexagonal’.
/geometry/lattices/lattice <uid>/pitch (double[])
Pitch of the lattice.
/geometry/lattices/lattice <uid>/outer (int)
Outer universe assigned to lattice cells outside the defined range.
/geometry/lattices/lattice <uid>/offsets (int[])
Offsets used for distribcell tally filter.
/geometry/lattices/lattice <uid>/universes (int[])
Three-dimensional array of universes assigned to each cell of the lattice.
/geometry/lattices/lattice <uid>/dimension (int[])
The number of lattice cells in each direction. This dataset is present only when the ‘type’ dataset is set to ‘rectangular’.
/geometry/lattices/lattice <uid>/lower_left (double[])
The coordinates of the lower-left corner of the lattice. This dataset is present only when the ‘type’ dataset is set to ‘rectangular’.
/geometry/lattices/lattice <uid>/n_rings (int)
Number of radial ring positions in the xy-plane. This dataset is present only when the ‘type’ dataset is set to ‘hexagonal’.
/geometry/lattices/lattice <uid>/n_axial (int)
Number of lattice positions along the z-axis. This dataset is present only when the ‘type’ dataset is set to ‘hexagonal’.
/geometry/lattices/lattice <uid>/center (double[])
Coordinates of the center of the lattice. This dataset is present only when the ‘type’ dataset is set to ‘hexagonal’.
/n_materials (int)
Number of materials in the problem.
/materials/material <uid>/index (int)
Index in materials array used internally in OpenMC.
/materials/material <uid>/name (char[])
Name of the material.
/materials/material <uid>/atom_density (double[])
Total atom density of the material in atom/b-cm.
/materials/material <uid>/nuclides (char[][])
Array of nuclides present in the material, e.g., ‘U-235.71c’.
/materials/material <uid>/nuclide_densities (double[])
Atom density of each nuclide.
/materials/material <uid>/sab_names (char[][])
Names of S(\(\alpha\),:math:beta) tables assigned to the material.
/tallies/n_tallies (int)
Number of tallies in the problem.
/tallies/n_meshes (int)
Number of meshes in the problem.
/tallies/mesh <uid>/index (int)
Index in the meshes array used internally in OpenMC.
/tallies/mesh <uid>/type (char[])
Type of the mesh. The only valid option is currently ‘regular’.
/tallies/mesh <uid>/dimension (int[])
Number of mesh cells in each direction.
/tallies/mesh <uid>/lower_left (double[])
Coordinates of the lower-left corner of the mesh.
/tallies/mesh <uid>/upper_right (double[])
Coordinates of the upper-right corner of the mesh.
/tallies/mesh <uid>/width (double[])
Width of a single mesh cell in each direction.
/tallies/tally <uid>/index (int)
Index in tallies array used internally in OpenMC.
/tallies/tally <uid>/name (char[])
Name of the tally.
/tallies/tally <uid>/n_filters (int)
Number of filters applied to the tally.
/tallies/tally <uid>/filter <j>/type (char[])
Type of the j-th filter. Can be ‘universe’, ‘material’, ‘cell’, ‘cellborn’, ‘surface’, ‘mesh’, ‘energy’, ‘energyout’, or ‘distribcell’.
/tallies/tally <uid>/filter <j>/offset (int)
Filter offset (used for distribcell filter).
/tallies/tally <uid>/filter <j>/paths (char[][])
The paths traversed through the CSG tree to reach each distribcell instance (for ‘distribcell’ filters only). This consists of the integer IDs for each universe, cell and lattice delimited by ‘->’. Each lattice cell is specified by its (x,y) or (x,y,z) indices.
/tallies/tally <uid>/filter <j>/n_bins (int)
Number of bins for the j-th filter.
/tallies/tally <uid>/filter <j>/bins (int[] or double[])
Value for each filter bin of this type.
/tallies/tally <uid>/nuclides (char[][])
Array of nuclides to tally. Note that if no nuclide is specified in the user input, a single ‘total’ nuclide appears here.
/tallies/tally <uid>/n_score_bins (int)
Number of scoring bins for a single nuclide. In general, this can be greater than the number of user-specified scores since each score might have multiple scoring bins, e.g., scatter-PN.
/tallies/tally <uid>/moment_orders (char[][])
Tallying moment orders for Legendre and spherical harmonic tally expansions (e.g., ‘P2’, ‘Y1,2’, etc.).
/tallies/tally <uid>/score_bins (char[][])
Scoring bins for the tally.