Uncertainty analysis of containment dose rate for core damage assessment in nuclear power plants

Guohua Wu; Jiejuan Tong; Yan Gao; Liguo Zhang; Yunfei Zhao

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자료유형: 학술저널

저자정보: Guohua Wu Jiejuan Tong Yan Gao Liguo Zhang Yunfei Zhao

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제50권 제5호

발행연도: 2018.1

수록면: 673 - 682 (10page)

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One of the most widely used methods to estimate core damage during a nuclear power plant accident iscontainment radiation measurement. The evolution of severe accidents is extremely complex, leading touncertainty in the containment dose rate (CDR). Therefore, it is difficult to accurately determine coredamage. This study proposes to conduct uncertainty analysis of CDR for core damage assessment. First,based on source term estimation, the Monte Carlo (MC) and point-kernel integration methods were usedto estimate the probability density function of the CDR under different extents of core damage in accidentscenarios with late containment failure. Second, the results were verified by comparing the resultsof both methods. The point-kernel integration method results were more dispersed than the MC results,and the MC method was used for both quantitative and qualitative analyses. Quantitative analysisindicated a linear relationship, rather than the expected proportional relationship, between the CDR andcore damage fraction. The CDR distribution obeyed a logarithmic normal distribution in accidents with asmall break in containment, but not in accidents with a large break in containment. A possible applicationof our analysis is a real-time core damage estimation program based on the CDR

참고문헌 (34)

참고문헌 신청

C.M. Allison / 2008 / An assessment of effectiveness of core exit temperatures with respect to PWR core damage state using RELAP/SCDAPSIM/MOD3.4 / Nucl. Eng. Des. 238:1547~1560

U.S. Nuclear Regulatory Commission (NRC) / 1980 / Clarification of TMI Action Plan Requirements, NUREG-0737

U.S. Westinghouse Electric Company LLC / 1984 / Westinghouse Owners Group Post Accident Core Damage Assessment Methodology

U.S. Nuclear Regulatory Commission / 1999 / Modifications Proposed by the Westinghouse Owners Group to the Core Damage Assessment Guidelines and Post Accident Sampling System Requirements

T. McKenna / 1996 / RTM-96 (NUREG/BR-0150). Response Technical Manual, vol. 1

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