ONIX

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ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers coupling with the open-source transport code OpenMC.

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# ONIX Nuclear Depletion Code

ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers coupling with the open-source transport code [OpenMC](https://github.com/openmc-dev/openmc).

The documentation for ONIX is hosted on Read the Docs: https://onix-documentation.readthedocs.io/en/latest/index.html

If you have questions or would like to contribute to the project please contact Julien: j.detroullioud@gmail.com

## Installation

[Installation
instructions](https://onix-documentation.readthedocs.io/en/latest/installation.html)
can be found in ONIX's documention.

## Citing

If you use ONIX in your research, please consider giving proper attribution by
citing the following publication:

-    Julien de Troullioud de Lanversin, Moritz Kütt, and Alexander Glaser, "[ONIX: An open-source depletion code](https://doi.org/10.1016/j.anucene.2020.107903),""
   *Ann. Nucl. Energy*, **151**, (2021).

## License

ONIX is distributed under the MIT/X
[license](https://onix-documentation.readthedocs.io/en/latest/license.html).

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