OpenMC Software Advances Nuclear Reactor Design, Wins R&D 100 Award
OpenMC, an open-source software developed by the U.S. Department of Energy's Argonne National Laboratory and MIT, has received an R&D 100 Award for its role in simulating nuclear fission and fusion systems. The software, which facilitates detailed modeling on high-performance computing systems, is widely used by national labs, universities, and private companies to design next-generation nuclear reactors and enhance safe, efficient nuclear energy solutions.
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OpenMC, an open-source software developed by the U.S. Department of Energy's Argonne National Laboratory and MIT, has won an R&D 100 Award. It aids researchers in simulating nuclear fission and fusion systems through virtual experiments.
The software predicts particle interactions and has become essential for designing next-generation nuclear reactors. OpenMC operates on high-performance computing systems, including exascale supercomputers, enabling detailed modeling of complex nuclear designs. The software is widely adopted by national labs, universities, and private companies, contributing to advancements in safe and efficient nuclear energy solutions.
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