3 citations · 4 across the 4 of their papers we have counts for
4 papers
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…
Efficiency calibration of the BRIKEN detector: the world largest counter for beta-delayed neutrons
M. Pallas, A. Tarifeno-Saldivia, F. Calvino +7
Beta-delayed neutron emission plays a fundamental role in the explosive nucleosynthesis of elements heavier than iron by the rapid neutron capture (r-process). The most ambitious p…
Calculation of kinetic parameters and with modified open source Monte Carlo code OpenMC(TD)
Jaime Romero-Barrientos, Jose Ignacio Marquez Damian, Francisco Molina +4
This work presents the methodology used to expand the capabilities of the Monte Carlo code OpenMC for the calculation of reactor kinetic parameters: effective delayed neutron fract…
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…