Litcius/Paper detail

Calculation of kinetic parameters β and Λ with modified open source Monte Carlo code OpenMC(TD)

J. Romero-Barrientos, José Ignacio Márquez Damián, F. Molina, Marcelo Zambra, P. Aguilera, Franco López-Usquiano, Byron Fernando Castillo Parra, Andrés Monares Ruiz

2021Nuclear Engineering and Technology17 citationsDOIOpen Access PDF

Abstract

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 fraction βeff and neutron generation time Λ. The modified code, OpenMC(Time-Dependent) or OpenMC(TD), was then used to calculate the effective delayed neutron fraction by using the prompt method, while the neutron generation time was estimated using the pulsed method, fitting Λ to the decay of the neutron population. OpenMC(TD) is intended to serve as an alternative for the estimation of kinetic parameters when licensed codes are not available. The results obtained are compared to experimental data and MCNP calculated values for 18 benchmark configurations.

Topics & Concepts

Monte Carlo methodNeutronBenchmark (surveying)Delayed neutronNuclear dataNeutron transportKinetic Monte CarloKinetic energyStatistical physicsPhysicsNuclear engineeringNuclear physicsComputational physicsPopulationMathematicsNeutron temperatureEngineeringStatisticsClassical mechanicsGeologySociologyGeodesyDemographyNuclear reactor physics and engineeringNuclear Physics and ApplicationsNuclear Materials and Properties