OpenMC is an open source Monte Carlo neutron and photon simulation transport code. Initially developed by the Computational Reactor Physics Group at MIT in 2011 as part of a project to develop scalable parallel algorithms for future exascale supercomputers, it has been contributed to by various universities, laboratories, and other institutions since its release to the public in December 2012.
OpenMC is an open source Monte Carlo neutron and photon simulation transport code. Initially developed by the Computational Reactor Physics Group at MIT in 2011 as part of a project to develop scalable parallel algorithms for future exascale supercomputers, it has been contributed to by various universities, laboratories, and other institutions since its release to the public in December 2012.
Source: Wikipedia "OpenMC" · CC BY-SA 4.0
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