Skip to content

samuelshaner/OpenMOC-shaner

Folders and files

NameName
Last commit message
Last commit date

Latest commit

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 

Repository files navigation

OpenMOC Method of Characteristics Neutral Particle Transport Code

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.

Installation

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

Troubleshooting

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.

License

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

About

Private copy of mit-crpg/OpenMOC for research development

Resources

Stars

Watchers

Forks

Releases

No releases published

Packages

No packages published