OpenMOC is a Method of Characteristics (MOC) neutral particle transport code for reactor physics criticality calculations. The OpenMOC project aims to be the first publicly available MOC code platform for full-core 3D reactor physics analysis. At the present time, it is capable of simulating 2D assembly and full-core reactor models based on constructive solid geometry with second-order surfaces. High-performance parallel solvers for multi-core CPUs and GPUs are actively pursued as part of the OpenMOC project. In addition, continued development of algorithmic acceleration techniques such as coarse mesh finite difference (CMFD) acceleration, are a focus of the OpenMOC project.

OpenMC was originally developed by members of the Computational Reactor Physics Group at the Massachusetts Institute of Technology starting in 2012. For more information on OpenMOC, feel free to send a message to the User’s Group mailing list.