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

J. Romero-Barrientos; J. I.Márquez Damián; F. Molina; M. Zambra; P. Aguilera; F. López-Usquiano; B. Parra; A. Ruiz

doi:10.1016/j.net.2021.09.020

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

J. Romero-Barrientos, J. I.Márquez Damián, F. Molina, M. Zambra, P. Aguilera, F. López-Usquiano, B. Parra, A. Ruiz

Research output: Contribution to journal › Article › peer-review

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 β_eff 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.

Original language	English
Journal	Nuclear Engineering and Technology
DOIs	https://doi.org/10.1016/j.net.2021.09.020
Publication status	Accepted/In press - 2021

Keywords

Effective delayed neutron fraction
Kinetic parameters
Monte Carlo
Neutron generation time
Open source
OpenMC

ASJC Scopus subject areas

Nuclear Energy and Engineering

Access to Document

10.1016/j.net.2021.09.020

Cite this

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

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.",

keywords = "Effective delayed neutron fraction, Kinetic parameters, Monte Carlo, Neutron generation time, Open source, OpenMC",

author = "J. Romero-Barrientos and Dami{\'a}n, {J. I.M{\'a}rquez} and F. Molina and M. Zambra and P. Aguilera and F. L{\'o}pez-Usquiano and B. Parra and A. Ruiz",

note = "Publisher Copyright: {\textcopyright} 2021 Korean Nuclear Society",

year = "2021",

doi = "10.1016/j.net.2021.09.020",

language = "English",

journal = "Nuclear Engineering and Technology",

issn = "1738-5733",

publisher = "Korean Nuclear Society",

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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.

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

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