针对裂变产额和半衰期的燃耗计算灵敏度和不确定度分析方法

Translated title of the contribution: Burnup Calculation Sensitivity and Uncertainty Analysis Method of Fission Yield and Decay Half-life

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3 Scopus citations

Abstract

The calculation model of sensitivity coefficient for decay half-life and fission product yield in burnup calculation was derived based on generalized perturbation theory, which considered the interaction between nuclear concentration and neutron flux. A code was developed to calculate sensitivity and uncertainty of effective neutron multiplication factors and nuclide concentration caused by nuclear data. Covariance matrix of fission yield for a simplified burnup library was generated based on standard deviation data of independent fission yield in evaluated nuclear data library to improve the accuracy of uncertainty quantification. Uncertainties induced by decay half-life and fission yield on infinite neutron multiplication factors and nuclide concentration for TMI-1 pin-cell in the UAM burnup benchmark were quantified based on ENDF/B-Ⅶ.1. The numerical results show that the uncertainty of infinite neutron multiplication factors induced by decay half-lives and fission yields is low, while the uncertainty of concentration of some fission product nuclide is high.

Translated title of the contributionBurnup Calculation Sensitivity and Uncertainty Analysis Method of Fission Yield and Decay Half-life
Original languageChinese (Traditional)
Pages (from-to)2323-2329
Number of pages7
JournalYuanzineng Kexue Jishu/Atomic Energy Science and Technology
Volume54
Issue number12
DOIs
StatePublished - 20 Dec 2020

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