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Determine whether nuclides are fissionable in volume calc mode - #3047
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pshriwise merged 3 commits intoJun 20, 2024
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Tiny suggestion here and then I think this should be good. Thanks @paulromano!
Co-authored-by: Patrick Shriwise <pshriwise@gmail.com>
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…c-dev#3047) Co-authored-by: Patrick Shriwise <pshriwise@gmail.com>
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…c-dev#3047) Co-authored-by: Patrick Shriwise <pshriwise@gmail.com>
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Description
This PR fixes a potential issue in sampling external source sites when OpenMC is loaded in volume calculation mode (which is used by the plotter). When running in volume calculation mode, we only load a select few attributes from nuclide .h5 files. Right now, we don't determine whether a nuclide is fissionable. However, for a proposed improvement to our plotter (see openmc-dev/plotter#131), it will be possible to sampling external source sites, which may require information on whether a material is fissionable if the "fissionable only" constraint is applied to the source. Without that information, a source with the "fissionable only" constraint will always be rejected because it won't think any material is fissionable (because the underlying nuclides aren't fissionable). This branch adds a small block of logic to determine if a nuclide is fissionable when it is loaded in volume calculation mode.
Checklist
I have followed the style guidelines for Python source files (if applicable)I have made corresponding changes to the documentation (if applicable)