TY - JOUR
T1 - Calculation of kinetic parameters βeff and Λ with modified open source Monte Carlo code OpenMC(TD)
AU - Romero-Barrientos, J.
AU - Damián, J. I.Márquez
AU - Molina, F.
AU - Zambra, M.
AU - Aguilera, P.
AU - López-Usquiano, F.
AU - Parra, B.
AU - Ruiz, A.
N1 - Publisher Copyright:
© 2021 Korean Nuclear Society
PY - 2021
Y1 - 2021
N2 - 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.
AB - 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.
KW - Effective delayed neutron fraction
KW - Kinetic parameters
KW - Monte Carlo
KW - Neutron generation time
KW - Open source
KW - OpenMC
UR - http://www.scopus.com/inward/record.url?scp=85115935807&partnerID=8YFLogxK
U2 - 10.1016/j.net.2021.09.020
DO - 10.1016/j.net.2021.09.020
M3 - Article
AN - SCOPUS:85115935807
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
SN - 1738-5733
ER -