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Clarify cell_wise MGXS fidelity and per-cell granularity in docs
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1 changed files with 13 additions and 2 deletions
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@ -678,10 +678,14 @@ one of "material_wise", "cell_wise", "stochastic_slab", or
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* Like ``material_wise``, but clones the material in each cell so every
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cell gets its own cross sections (each material-filled cell is assigned a
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distinct macroscopic).
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- * Resolves intra-material spatial variation that ``material_wise`` averages
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away, e.g. a thick shield or a steep flux gradient within a single material
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- * Resolves spatial variation between distinct cells that share a material,
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which ``material_wise`` averages away (e.g. a shield wall modelled as
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several cells of one material, each covering a different depth)
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* Captures spatial self shielding between cells filled with the same material
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- * Most expensive (one cross section set per cell) and a larger library
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* Fidelity is limited by the cell definitions, not the source region mesh:
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a single large cell uses one cross section set throughout, so a steep
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gradient is only resolved if the geometry is split into several cells
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* Same far-from-source limitation as ``material_wise``: a cell that is not
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tallied to yields zero cross sections for that cell
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* - ``stochastic_slab``
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@ -702,6 +706,13 @@ one of "material_wise", "cell_wise", "stochastic_slab", or
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between materials)
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* May hang if a material has a k-infinity greater than 1.0
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.. note::
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The ``cell_wise`` method generates one cross section set per cell definition,
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not per cell instance. A cell that appears in several locations of a lattice
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therefore shares a single cross section set across all of those locations. If
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you need distinct cross sections per instance, subdivide the geometry into
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separate cells.
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When selecting a non-default energy group structure, you can manually define
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group boundaries or specify the name of a known group structure (a list of which
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can be found at :data:`openmc.mgxs.GROUP_STRUCTURES`). The ``nparticles``
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