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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2022.3
- 수록면
- 811 - 816 (6page)
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This work presents the methodology used to expand the capabilities of the Monte Carlo code OpenMC forthe calculation of reactor kinetic parameters: effective delayed neutron fraction beff and neutron generationtime L. The modified code, OpenMC(Time-Dependent) or OpenMC(TD), was then used tocalculate the effective delayed neutron fraction by using the prompt method, while the neutron generationtime was estimated using the pulsed method, fitting L to the decay of the neutron population.
OpenMC(TD) is intended to serve as an alternative for the estimation of kinetic parameters whenlicensed codes are not available. The results obtained are compared to experimental data and MCNPcalculated values for 18 benchmark configurations.
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