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

Authors :
Romero-Barrientos, J.
Damián, J.I. Márquez
Molina, F.
Zambra, M.
Aguilera, P.
López-Usquiano, F.
Parra, B.
Ruiz, A.
Source :
Nuclear Engineering and Technology; 20210101, Issue: Preprints
Publication Year :
2021

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 βeffand 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.

Details

Language :
English
ISSN :
17385733 and 2234358X
Issue :
Preprints
Database :
Supplemental Index
Journal :
Nuclear Engineering and Technology
Publication Type :
Periodical
Accession number :
ejs57897559
Full Text :
https://doi.org/10.1016/j.net.2021.09.020