US: Award-winning Monte Carlo code optimizes nuclear reactor designs

OpenMC is a powerful, open-source Monte Carlo simulation software developed collaboratively by the US Department of Energy’s Argonne National Laboratory and MIT. Recently awarded an R&D 100 Award, OpenMC enables researchers to conduct detailed virtual experiments that accelerate innovation in both nuclear fission and fusion reactor designs. By simulating the behavior of neutrons and photons within complex systems, the software helps predict fuel consumption rates and radiation damage, allowing developers to optimize reactor safety and performance without costly physical prototypes. A key strength of OpenMC lies in its ability to leverage high-performance computing resources, including exascale supercomputers like Aurora and Frontier, to perform simulations with unprecedented detail and speed. Its open-source nature fosters widespread adoption and collaboration among universities, private companies, and international researchers. Beyond advancing nuclear energy technologies, OpenMC also supports applications in used nuclear fuel management and radiation protection for medical and space environments. The software’s flexible interface and compatibility with diverse hardware—from personal laptops to supercomputers—make it a