OpenMC Software Advances Nuclear Fusion and Fission Reactor Simulations
OpenMC, an open-source software developed by Argonne National Laboratory and MIT, enhances nuclear fission and fusion reactor simulations by predicting subatomic particle behavior, thereby improving safety and efficiency. Recently awarded the R&D-100-Award, it facilitates virtual experiments to expedite development processes, with widespread adoption across national labs, universities, and private firms, particularly in the US and Europe, supported by the DOE's Fusion Energy Sciences program. Optimized for exascale supercomputers, OpenMC allows for precise reactor simulations, benefiting from collaborative contributions from its developers.
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OpenMC, developed by Argonne National Laboratory and MIT, is an open-source software that predicts subatomic particle behavior in reactor designs, enhancing safety and efficiency in nuclear fission and fusion. Awarded the R&D-100-Award, OpenMC enables virtual experiments to accelerate developments before costly prototypes.
Its adoption spans national labs, universities, and private firms, particularly in the US and Europe, supported by the DOE's Fusion Energy Sciences program. OpenMC has been optimized for exascale supercomputers, allowing precise simulations of reactors, with contributions from Argonne and MIT researchers.
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