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

Research output: Contribution to journalArticlepeer-review

6 Citations (Scopus)


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.

Original languageEnglish
JournalNuclear Engineering and Technology
Publication statusAccepted/In press - 2021


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

ASJC Scopus subject areas

  • Nuclear Energy and Engineering


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