Welcome to the OpenMOC repository! OpenMOC is a simulation tool for solving for the flux, power distribution, and multiplication factor within a nuclear reactor. The code employs the deterministic method of characteristics using source iteration. The OpenMOC project aims to provide a simple-to-use Python package bound to a back-end of source code written in C/C++ and CUDA. It includes support for constructive solid geometry and 2D ray tracing for fully heterogeneous multi-group calculations. Development of OpenMOC began at MIT in 2012 and is spearheaded by several graduate students in the Nuclear Science & Engineering Department.

Complete documentation on the usage of OpenMOC is hosted at https://mit-crpg.github.io/OpenMOC/. If you would like to contribute to the OpenMOC project, please contact the development team.

Detailed installation instructions can be found in the User's Guide.

If you run into problems installing or running OpenMOC, first review the FAQ in the User's Guide. If you are unable to find a solution to your problem there, please contact one of the developers.

OpenMOC is approved for distribution under the MIT/X license.