OpenMC Monte Carlo Particle Transport Code
The OpenMC project aims to provide a fully-featured Monte Carlo particle
transport code based on modern methods. It is a constructive solid geometry,
continuous-energy transport code that uses HDF5 format cross sections. The
project started under the Computational Reactor Physics Group at MIT.
Complete documentation on the usage of OpenMC is hosted on Read the Docs (both
for the latest release and
developmental version). If you are
interested in the project, or would like to help and contribute, please get in
touch on the OpenMC discussion forum.
Installation
Detailed installation
instructions
can be found in the User's Guide.
Citing
If you use OpenMC in your research, please consider giving proper attribution by
citing the following publication:
Troubleshooting
If you run into problems compiling, installing, or running OpenMC, first check
the Troubleshooting
section in the
User's Guide. If you are not able to find a solution to your problem there,
please post to the discussion forum.
Reporting Bugs
OpenMC is hosted on GitHub and all bugs are reported and tracked through the
Issues feature on GitHub.
However, GitHub Issues should not be used for common troubleshooting purposes.
If you are having trouble installing the code or getting your model to run
properly, you should first send a message to the discussion
forum. If it turns out your issue really is a
bug in the code, an issue will then be created on GitHub. If you want to request
that a feature be added to the code, you may create an Issue on github.
License
OpenMC is distributed under the MIT/X
license.
