Open-source tool opens new paths for nuclear innovation
The OpenMC software package, developed by Argonne National Laboratory and MIT, is gaining wide adoption as an open-source platform for simulating neutron and photon behavior in next-generation fission and fusion systems. The tool allows universities, startups and national laboratories worldwide to run high-fidelity models on everything from laptops to exascale supercomputers. Using Monte Carlo algorithms, it can predict fuel burnup, radiation damage and stem behaviors before physical prototypes are built.