-In order to perform depletion analysis using [the OpenMC depletion module](https://docs.openmc.org/en/latest/pythonapi/deplete.html), a representation of the depletion chain must be presented. This chain describes transmutation and decay channels causing isotopes to evolve over time. XML-representations of these depletion chains can be built using evaluated nuclear data libraries. OpenMC provides [functions](https://docs.openmc.org/en/latest/pythonapi/generated/openmc.deplete.Chain.html#openmc.deplete.Chain.from_endf) and scripts to generate these chain files using a collection of neutron interaction, neutron-induced fission, and decay files. Alternatively, three pre-generated chain files are made available using [ENDF/B-VII.1 data distributed with OpenMC](http://openmc.org/official-data-libraries/).
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