Home
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 fixed source iteration. Development of OpenMOC began at MIT in 2012 and is spearheaded by several graduate students at MIT's Nuclear Science & Engineering Department.
OpenMOC is written in C++ and makes use of a couple of external C++ libraries for I\O. We hope that you will give OpenMOC a try yourself. A number of helpful links are given below to help you get started with using the code. As OpenMOC continues to undergo development, we ask that you report any issues or concerns to one of our developers.
A few of the features which we plan to implement for future versions of OpenMOC include parallelizing the method of characteristics solver using OpenMP, development of the code for GPUs, extending the code into the time domain, and Course Mesh Finite Difference acceleration. If you have ideas for other ways to improve the code, please let us know.
