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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.

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 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:

License

ONIX is distributed under the MIT/X license.

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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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