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https://github.com/openmc-dev/openmc.git
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Complete documentation of summary file format, including suggestions from
@wbinventor.
This commit is contained in:
parent
dd5b288b03
commit
759f96c9e0
4 changed files with 254 additions and 137 deletions
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@ -1426,8 +1426,7 @@ a separate element with the tag name ``<mesh>``. This element has the following
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attributes/sub-elements:
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:type:
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The type of structured mesh. Valid options include "rectangular" and
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"hexagonal".
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The type of structured mesh. The only valid option is "regular".
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:dimension:
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The number of mesh cells in each direction.
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@ -56,7 +56,7 @@ The current revision of the statepoint file format is 13.
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The number of batches already simulated.
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if (run_mode == MODE_EIGENVALUE)
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if run_mode == 'k-eigenvalue':
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**/n_inactive** (*int*)
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@ -136,31 +136,29 @@ if (run_mode == MODE_EIGENVALUE)
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User-identified unique ID of each mesh
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*do i = 1, n_meshes*
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**/tallies/meshes/mesh <uid>/id** (*int*)
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**/tallies/meshes/mesh i/id** (*int*)
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Unique identifier of the mesh.
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Unique identifier of the mesh.
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**/tallies/meshes/mesh <uid>/type** (*char[]*)
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**/tallies/meshes/mesh i/type** (*char[]*)
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Type of mesh.
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Type of mesh.
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**/tallies/meshes/mesh <uid>/dimension** (*int*)
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**/tallies/meshes/mesh i/dimension** (*int*)
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Number of mesh cells in each dimension.
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Number of mesh cells in each dimension.
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**/tallies/meshes/mesh <uid>/lower_left** (*double[]*)
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**/tallies/meshes/mesh i/lower_left** (*double[]*)
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Coordinates of lower-left corner of mesh.
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Coordinates of lower-left corner of mesh.
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**/tallies/meshes/mesh <uid>/upper_right** (*double[]*)
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**/tallies/meshes/mesh i/upper_right** (*double[]*)
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Coordinates of upper-right corner of mesh.
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Coordinates of upper-right corner of mesh.
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**/tallies/meshes/mesh <uid>/width** (*double[]*)
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**/tallies/meshes/mesh i/width** (*double[]*)
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Width of each mesh cell in each dimension.
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Width of each mesh cell in each dimension.
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**/tallies/n_tallies** (*int*)
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@ -174,63 +172,66 @@ if (run_mode == MODE_EIGENVALUE)
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User-identified unique ID of each tally.
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*do i = 1, n_tallies*
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**/tallies/tally <uid>/estimator** (*char[]*)
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**/tallies/tally i/estimator** (*char[]*)
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Type of tally estimator, either 'analog', 'tracklength', or 'collision'.
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Type of tally estimator.
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**/tallies/tally <uid>/n_realizations** (*int*)
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**/tallies/tally i/n_realizations** (*int*)
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Number of realizations.
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Number of realizations.
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**/tallies/tally <uid>/n_filters** (*int*)
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**/tallies/tally i/n_filters** (*int*)
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Number of filters used.
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Number of filters used.
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**/tallies/tally <uid>/filter <j>/type** (*char[]*)
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*do j = 1, tallies(i) % n_filters*
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Type of the j-th filter. Can be 'universe', 'material', 'cell', 'cellborn',
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'surface', 'mesh', 'energy', 'energyout', or 'distribcell'.
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**/tallies/tally i/filter j/type** (*char[]*)
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**/tallies/tally <uid>/filter <j>/offset** (*int*)
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Type of tally filter.
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Filter offset (used for distribcell filter).
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**/tallies/tally i/filter j/offset** (*int*)
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**/tallies/tally <uid>/filter <j>/n_bins** (*int*)
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Filter offset (used for distribcell).
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Number of bins for the j-th filter.
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**/tallies/tally i/filter j/n_bins** (*int*)
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**/tallies/tally <uid>/filter <j>/bins** (*int[]* or *double[]*)
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Number of bins for filter.
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Value for each filter bin of this type.
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**/tallies/tally i/filter j/bins** (*int[]* or *double[]*)
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**/tallies/tally <uid>/nuclides** (*char[][]*)
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Value for each filter bin of this type.
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Array of nuclides to tally. Note that if no nuclide is specified in the user
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input, a single 'total' nuclide appears here.
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**/tallies/tally i/nuclides** (*char[][]*)
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**/tallies/tally <uid>/n_score_bins** (*int*)
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Values of specified nuclide bins.
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Number of scoring bins for a single nuclide. In general, this can be greater
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than the number of user-specified scores since each score might have
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multiple scoring bins, e.g., scatter-PN.
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**/tallies/tally i/n_score_bins** (*int*)
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**/tallies/tally <uid>/score_bins** (*char[][]*)
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Number of scores.
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Values of specified scores.
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**/tallies/tally i/score_bins** (*char[][]*)
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**/tallies/tally <uid>/n_user_scores** (*int*)
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Values of specified scores.
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Number of scores without accounting for those added by expansions,
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e.g. scatter-PN.
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**/tallies/tally i/n_user_scores** (*int*)
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**/tallies/tally <uid>/moment_orders** (*char[][]*)
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Number of scores without accounting for those added by expansions,
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e.g. scatter-PN.
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Tallying moment orders for Legendre and spherical harmonic tally expansions
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(*e.g.*, 'P2', 'Y1,2', etc.).
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**/tallies/tally i/moment_orders** (*char[][]*)
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**/tallies/tally <uid>/results** (Compound type)
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Tallying moment orders for Legendre and spherical harmonic tally
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expansions (*e.g.*, 'P2', 'Y1,2', etc.).
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**/tallies/tally i/results** (Compound type)
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Accumulated sum and sum-of-squares for each bin of the i-th tally.
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Accumulated sum and sum-of-squares for each bin of the i-th tally. This is a
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two-dimensional array, the first dimension of which represents combinations
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of filter bins and the second dimensions of which represents scoring
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bins. Each element of the array has fields 'sum' and 'sum_sq'.
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**/source_present** (*int*)
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@ -29,7 +29,7 @@ The current revision of the summary file format is 1.
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**/date_and_time** (*char[]*)
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Date and time the state point was written.
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Date and time the summary was written.
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**/n_procs** (*int*)
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@ -43,186 +43,302 @@ The current revision of the summary file format is 1.
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Number of batches to simulate.
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if (run_mode == MODE_EIGENVALUE)
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**/n_inactive** (*int*)
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**/n_inactive** (*int*)
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Number of inactive batches. Only present if /run_mode is set to
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'k-eigenvalue'.
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Number of inactive batches.
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**/n_active** (*int*)
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**/n_active** (*int*)
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Number of active batches. Only present if /run_mode is set to
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'k-eigenvalue'.
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Number of active batches.
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**/gen_per_batch** (*int*)
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**/gen_per_batch** (*int*)
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Number of generations per batch.
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end if
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Number of generations per batch. Only present if /run_mode is set to
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'k-eigenvalue'.
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**/geometry/n_cells** (*int*)
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Number of cells in the problem.
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**/geometry/n_surfaces** (*int*)
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Number of surfaces in the problem.
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**/geometry/n_universes** (*int*)
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Number of unique universes in the problem.
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**/geometry/n_lattices** (*int*)
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do i = 1, n_cells
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Number of lattices in the problem.
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**/geometry/cells/cell <uid>/index** (*int*)
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**/geometry/cells/cell <uid>/index** (*int*)
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**/geometry/cells/cell <uid>/name** (*char[]*)
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Index in cells array used internally in OpenMC.
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**/geometry/cells/cell <uid>/universe** (*int*)
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**/geometry/cells/cell <uid>/name** (*char[]*)
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**/geometry/cells/cell <uid>/fill_type** (*char[]*)
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Name of the cell.
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**/geometry/cells/cell <uid>/material** (*int*)
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**/geometry/cells/cell <uid>/universe** (*int*)
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**/geometry/cells/cell <uid>/maps** (*int*)
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Universe assigned to the cell. If none is specified, the default
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universe (0) is assigned.
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**/geometry/cells/cell <uid>/offset** (*int[]*)
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**/geometry/cells/cell <uid>/fill_type** (*char[]*)
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**/geometry/cells/cell <uid>/translated** (*int*)
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Type of fill for the cell. Can be 'normal', 'universe', or 'lattice'.
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**/geometry/cells/cell <uid>/translation** (*double[]*)
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**/geometry/cells/cell <uid>/material** (*int*)
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**/geometry/cells/cell <uid>/rotated** (*int*)
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Unique ID of the material assigned to the cell. This dataset is present only
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if fill_type is set to 'normal'.
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**/geometry/cells/cell <uid>/rotation** (*double[]*)
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**/geometry/cells/cell <uid>/maps** (*int*)
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**/geometry/cells/cell <uid>/lattice** (*int*)
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TODO: Add description.
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**/geometry/cells/cell <uid>/surfaces** (*int[]*)
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**/geometry/cells/cell <uid>/offset** (*int[]*)
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end do
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Offset used for distribcell tally filter. This dataset is present only if
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fill_type is set to 'universe'.
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do i = 1, n_surfaces
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**/geometry/cells/cell <uid>/translated** (*int*)
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**/geometry/surfaces/surface <uid>/index** (*int*)
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Indicates if a translation is to be applied to the fill universe if one is
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present. Note that this dataset assumes values of 0 or 1. This dataset is
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present only if fill_type is set to 'universe'.
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**/geometry/surfaces/surface <uid>/name** (*char[]*)
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**/geometry/cells/cell <uid>/translation** (*double[3]*)
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**/geometry/surfaces/surface <uid>/type** (*char[]*)
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Translation applied to the fill universe. This dataset is present only if
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fill_type is set to 'universe'.
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**/geometry/surfaces/surface <uid>/coefficients** (*double[]*)
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**/geometry/cells/cell <uid>/rotated** (*int*)
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**/geometry/surfaces/surface <uid>/boundary_condition** (*char[]*)
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Indicates if a rotation is to be applied to the fill universe if one is
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present. Note that this dataset assumes values of 0 or 1. This dataset is
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present only if fill_type is set to 'universe'.
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end do
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**/geometry/cells/cell <uid>/rotation** (*double[3]*)
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do i = 1, n_universes
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Angles in degrees about the x-, y-, and z-axes for which the fill universe
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should be rotated. This dataset is present only if fill_type is set to
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'universe'.
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**/geometry/universes/universe <uid>/index** (*int*)
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**/geometry/cells/cell <uid>/lattice** (*int*)
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**/geometry/universes/universe <uid>/cells** (*int[]*)
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Unique ID of the lattice which fills the cell. Only present if fill_type is
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set to 'lattice'.
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end do
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**/geometry/cells/cell <uid>/surfaces** (*int[]*)
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do i = 1, n_lattices
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Surface specification for the cell.
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**/geometry/lattices/lattice <uid>/index** (*int*)
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**/geometry/surfaces/surface <uid>/index** (*int*)
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**/geometry/lattices/lattice <uid>/name** (*char[]*)
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Index in surfaces array used internally in OpenMC.
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**/geometry/lattices/lattice <uid>/type** (*char[]*)
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**/geometry/surfaces/surface <uid>/name** (*char[]*)
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**/geometry/lattices/lattice <uid>/pitch** (*double[]*)
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Name of the surface.
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**/geometry/lattices/lattice <uid>/outer** (*int*)
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**/geometry/surfaces/surface <uid>/type** (*char[]*)
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**/geometry/lattices/lattice <uid>/offset_size** (*int[]*)
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Type of the surface. Can be 'X Plane', 'Y Plane', 'Z Plane', 'Plane', 'X
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Cylinder', 'Y Cylinder', 'Sphere', 'X Cone', 'Y Cone', or 'Z Cone'.
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**/geometry/lattices/lattice <uid>/maps** (*int*)
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**/geometry/surfaces/surface <uid>/coefficients** (*double[]*)
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**/geometry/lattices/lattice <uid>/offsets** (*int[]*)
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Array of coefficients that define the surface. See :ref:`surface_element`
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for what coefficients are defined for each surface type.
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**/geometry/lattices/lattice <uid>/universes** (*int[]*)
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**/geometry/surfaces/surface <uid>/boundary_condition** (*char[]*)
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if (rectangular lattice)
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Boundary condition applied to the surface. Can be 'transmission', 'vacuum',
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'reflective', or 'periodic'.
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**/geometry/lattices/lattice <uid>/dimension** (*int[]*)
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**/geometry/universes/universe <uid>/index** (*int*)
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**/geometry/lattices/lattice <uid>/lower_left** (*double[]*)
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Index in the universes array used internally in OpenMC.
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elseif (hexagonal lattice)
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**/geometry/universes/universe <uid>/cells** (*int[]*)
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**/geometry/lattices/lattice <uid>/n_rings** (*int*)
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Array of unique IDs of cells that appear in the universe.
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**/geometry/lattices/lattice <uid>/n_axial** (*int*)
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**/geometry/lattices/lattice <uid>/index** (*int*)
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**/geometry/lattices/lattice <uid>/center** (*double[]*)
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Index in the lattices array used internally in OpenMC.
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end if
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**/geometry/lattices/lattice <uid>/name** (*char[]*)
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end do
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Name of the lattice.
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**/geometry/lattices/lattice <uid>/type** (*char[]*)
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Type of the lattice, either 'rectangular' or 'hexagonal'.
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**/geometry/lattices/lattice <uid>/pitch** (*double[]*)
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Pitch of the lattice.
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**/geometry/lattices/lattice <uid>/outer** (*int*)
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Outer universe assigned to lattice cells outside the defined range.
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**/geometry/lattices/lattice <uid>/offset_size** (*int[]*)
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TODO: Explain offset_size
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**/geometry/lattices/lattice <uid>/maps** (*int*)
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TODO: Explain maps
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**/geometry/lattices/lattice <uid>/offsets** (*int[]*)
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Offsets used for distribcell tally filter.
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**/geometry/lattices/lattice <uid>/universes** (*int[]*)
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Three-dimensional array of universes assigned to each cell of the lattice.
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**/geometry/lattices/lattice <uid>/dimension** (*int[]*)
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The number of lattice cells in each direction. This dataset is present only
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when the 'type' dataset is set to 'rectangular'.
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**/geometry/lattices/lattice <uid>/lower_left** (*double[]*)
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The coordinates of the lower-left corner of the lattice. This dataset is
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present only when the 'type' dataset is set to 'rectangular'.
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**/geometry/lattices/lattice <uid>/n_rings** (*int*)
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Number of radial ring positions in the xy-plane. This dataset is present
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only when the 'type' dataset is set to 'hexagonal'.
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**/geometry/lattices/lattice <uid>/n_axial** (*int*)
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Number of lattice positions along the z-axis. This dataset is present only
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when the 'type' dataset is set to 'hexagonal'.
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**/geometry/lattices/lattice <uid>/center** (*double[]*)
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Coordinates of the center of the lattice. This dataset is present only when
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the 'type' dataset is set to 'hexagonal'.
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**/n_materials** (*int*)
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do i = 1, n_materials
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Number of materials in the problem.
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**/materials/material <uid>/index** (*int*)
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**/materials/material <uid>/index** (*int*)
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**/materials/material <uid>/name** (*char[]*)
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Index in materials array used internally in OpenMC.
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**/materials/material <uid>/atom_density** (*double[]*)
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**/materials/material <uid>/name** (*char[]*)
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**/materials/material <uid>/nuclides** (*int[]*)
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Name of the material.
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**/materials/material <uid>/nuclide_densities** (*double[]*)
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**/materials/material <uid>/atom_density** (*double[]*)
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**/materials/material <uid>/sab_names** (*char[][]*)
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Total atom density of the material in atom/b-cm.
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end do
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**/materials/material <uid>/nuclides** (*char[][]*)
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Array of nuclides present in the material, e.g., 'U-235.71c'.
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**/materials/material <uid>/nuclide_densities** (*double[]*)
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Atom density of each nuclide.
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**/materials/material <uid>/sab_names** (*char[][]*)
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Names of S(:math:`\alpha`,:math:`\beta`) tables assigned to the material.
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**/tallies/n_tallies** (*int*)
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Number of tallies in the problem.
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**/tallies/n_meshes** (*int*)
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do i = 1, n_meshes
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Number of meshes in the problem.
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**/tallies/mesh <uid>/index** (*int*)
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**/tallies/mesh <uid>/index** (*int*)
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||||
**/tallies/mesh <uid>/type** (*char[]*)
|
||||
Index in the meshes array used internally in OpenMC
|
||||
|
||||
**/tallies/mesh <uid>/dimension** (*int[]*)
|
||||
**/tallies/mesh <uid>/type** (*char[]*)
|
||||
|
||||
**/tallies/mesh <uid>/lower_left** (*double[]*)
|
||||
Type of the mesh. The only valid option is currently 'regular'.
|
||||
|
||||
**/tallies/mesh <uid>/upper_right** (*double[]*)
|
||||
**/tallies/mesh <uid>/dimension** (*int[]*)
|
||||
|
||||
**/tallies/mesh <uid>/width** (*double[]*)
|
||||
Number of mesh cells in each direction.
|
||||
|
||||
end do
|
||||
**/tallies/mesh <uid>/lower_left** (*double[]*)
|
||||
|
||||
do i = 1, n_tallies
|
||||
Coordinates of the lower-left corner of the mesh.
|
||||
|
||||
**/tallies/tally <uid>/index** (*int*)
|
||||
**/tallies/mesh <uid>/upper_right** (*double[]*)
|
||||
|
||||
**/tallies/tally <uid>/name** (*char[]*)
|
||||
Coordinates of the upper-right corner of the mesh.
|
||||
|
||||
**/tallies/tally <uid>/total_score_bins** (*int*)
|
||||
**/tallies/mesh <uid>/width** (*double[]*)
|
||||
|
||||
**/tallies/tally <uid>/total_filter_bins** (*int*)
|
||||
Width of a single mesh cell in each direction.
|
||||
|
||||
**/tallies/tally <uid>/n_filters** (*int*)
|
||||
**/tallies/tally <uid>/index** (*int*)
|
||||
|
||||
do j = 1, n_filters
|
||||
Index in tallies array used internally in OpenMC.
|
||||
|
||||
**/tallies/tally <uid>/filter j/type** (*char[]*)
|
||||
**/tallies/tally <uid>/name** (*char[]*)
|
||||
|
||||
**/tallies/tally <uid>/filter j/n_bins** (*int*)
|
||||
Name of the tally.
|
||||
|
||||
**/tallies/tally <uid>/filter j/bins** (*int[]* or *double[]*)
|
||||
**/tallies/tally <uid>/total_score_bins** (*int*)
|
||||
|
||||
**/tallies/tally <uid>/filter j/type_name** (*char[]*)
|
||||
Total number of scoring bins for all nuclides. This is used as the size of
|
||||
second dimension of the tally results array.
|
||||
|
||||
end do
|
||||
**/tallies/tally <uid>/total_filter_bins** (*int*)
|
||||
|
||||
**/tallies/tally <uid>/nuclides** (*char[][]*)
|
||||
Total number of filter bins accounting for all filters. This is used as the
|
||||
size of first dimension of the tally results array.
|
||||
|
||||
**/tallies/tally <uid>/n_score_bins** (*int*)
|
||||
**/tallies/tally <uid>/n_filters** (*int*)
|
||||
|
||||
**/tallies/tally <uid>/score_bins** (*char[][]*)
|
||||
Number of filters applied to the tally.
|
||||
|
||||
end do
|
||||
**/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>/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>/score_bins** (*char[][]*)
|
||||
|
||||
Scoring bins for the tally.
|
||||
|
|
|
|||
|
|
@ -515,6 +515,7 @@ contains
|
|||
filter_group = create_group(tally_group, "filter " // trim(to_str(j)))
|
||||
|
||||
! Write number of bins for this filter
|
||||
call write_dataset(filter_group, "offset", t%filters(j)%offset)
|
||||
call write_dataset(filter_group, "n_bins", t%filters(j)%n_bins)
|
||||
|
||||
! Write filter bins
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue