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

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 calcul...

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Detalles Bibliográficos
Autores: Romero Barrientos, J., Marquez Damian, Jose Ignacio, Molina, F., Zambra, M., Aguilera, P., López Usquiano, F., Parra, B., Ruiz, A.
Tipo de recurso: artículo
Estado:Versión publicada
Fecha de publicación:2022
País:Argentina
Institución:Consejo Nacional de Investigaciones Científicas y Técnicas
Repositorio:CONICET Digital (CONICET)
Idioma:inglés
OAI Identifier:oai:ri.conicet.gov.ar:11336/188157
Acceso en línea:http://hdl.handle.net/11336/188157
Access Level:acceso abierto
Palabra clave:EFFECTIVE DELAYED NEUTRON FRACTION
KINETIC PARAMETERS
MONTE CARLO
NEUTRON GENERATION TIME
OPEN SOURCE
OPENMC
https://purl.org/becyt/ford/2.3
https://purl.org/becyt/ford/2
Descripción
Sumario: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.

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