Difference between revisions of "Openmc"
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Latest revision as of 20:25, 21 February 2024
Description
OpenMC is a community-developed Monte Carlo neutron and photon transport simulation code.
Environment Modules
Run module spider openmc to find out what environment modules are available for this application.
System Variables
- HPC_OPENMC_DIR - installation directory
- HPC_OPENMC_BIN - executable directory
Citation
If you publish research that uses openmc you have to cite it as follows:
Paul K. Romano, Nicholas E. Horelik, Bryan R. Herman, Adam G. Nelson, Benoit Forget, and Kord Smith, “OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development,” Ann. Nucl. Energy, 82, 90–97 (2015).