Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark

Chaudri, Khurrum Saleem; Mirza, Sikander M.

doi:10.1016/j.pnucene.2014.12.018

Cited by 21 publications

(2 citation statements)

References 5 publications

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“…This code is open source, and its license allows to modify the source code to develop and add new capabilities. An example of this last point is the many number of publications associated to the code, covering topics and developments such as benchmarking [7], coupling and multi-physics [8], geometry and visualization [9], multigroup cross section generation [10], doppler broadening [11], nuclear data [12], parallelism [13], depletion [14] and sensitivity analysis [15].…”

Section: Openmc Monte Carlo Codementioning

confidence: 99%

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Calculation of kinetic parameters $β_{\mathit{eff}}$ and $Λ$ with modified open source Monte Carlo code OpenMC(TD)

Romero-Barrientos,

Damian,

Molina

et al. 2021

Preprint

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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.

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