Clarify cell_wise MGXS fidelity and per-cell granularity in docs

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shimwell 2026-07-21 11:52:08 +02:00
parent 3bc19ef017
commit f8e3d36d0b

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