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 instructions can be found in ONIX's documention.

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,"" Ann. Nucl. Energy, 151, (2021).

ONIX is distributed under the MIT/X license.