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```
# TODO @je-cook: get shield material
```
https://github.com/Fusion-Power-Plant-Framework/bluemira/blob/1d69601c1fb0ae5f05a664f0fad452190caf587b/bluemira/radiation_transport/neutronics/bla…
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We currently have a limited number of "standard materials" available.
This should be expanded to includ…
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The `armi/tests/` directory has a bunch of unorganized data files. I would like these to be organized.
> For instance, there are three YAML files to define the ZPPR benchmark reactor, those could g…
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## Description of issue / requirement to address
The STP CAD output files need material metadata attached to volumes or groups of volumes so that it can be more easily used in neutronics analysis. Th…
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thinking about how to use this code with openmc and I often have the situation where the fusion reactor is quotes as 1GW fusion power and then there is a need to find number of fusion reactions from t…
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Add tests for the radiation_transport/neutronics folder as there are none
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I have a case that runs many cycles and has a lot of assembly definitions. Many of these assembly definitions are not present in the initial core. Some of those have their own unique XS ID.
I've n…
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Please note that I'm not too knowledgeable with the code, so feel free to comment angry messages and close the issue if this is in error :)
For example, for ENDF-B-VII.1-neutrons n-008-O_017.endf,…
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In the code chunk below, we store `coupledIteration` as `n+1`, whereas we send `n` into `interactAllCOupled()`:
https://github.com/terrapower/armi/blob/eef58ddcd797c7acc542a4941b95dcb84dda2670/armi/o…