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physics.comp-ph2025
Extending OpenMC Validation to Spent Fuel Canisters: A Criticality Benchmark Against MCNP
Javier Ruiz-Pineda, Jaime Romero-Barrientos, Francisco Molina +2
OpenMC is an open-source Monte Carlo code with increasing relevance in criticality safety and reactor physics applications. While its validation has covered a broad range of system…
physics.comp-ph2021★ 3 cited
Time-dependent Monte Carlo in fissile systems with beta-delayed neutron precursors
Jaime Romero-Barrientos
In the field of nuclear reactor physics, transient phenomena are usually studied using deterministic or hybrids methods. These methods require many approximations, such as: geometr…