Uncertainty Analysis of Reactor Structure Material Activation Calculation Induced From Nuclear Data

Wu Jiebo; Wu Jiebo; Yang Chao; Yang Chao; Yu Tao; Yu Tao; Chen Zhenping; Chen Zhenping

doi:10.3389/fenrg.2022.841998

Frontiers in Energy Research (Feb 2022)

Uncertainty Analysis of Reactor Structure Material Activation Calculation Induced From Nuclear Data

Wu Jiebo,
Wu Jiebo,
Yang Chao,
Yang Chao,
Yu Tao,
Yu Tao,
Chen Zhenping,
Chen Zhenping

Affiliations

Wu Jiebo: School of Nuclear Science and Technology, University of South China, Hengyang, China
Wu Jiebo: Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, China
Yang Chao: School of Nuclear Science and Technology, University of South China, Hengyang, China
Yang Chao: Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, China
Yu Tao: School of Nuclear Science and Technology, University of South China, Hengyang, China
Yu Tao: Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, China
Chen Zhenping: School of Nuclear Science and Technology, University of South China, Hengyang, China
Chen Zhenping: Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang, China

DOI: https://doi.org/10.3389/fenrg.2022.841998
Journal volume & issue: Vol. 10

Abstract

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Highly accurate activation calculations are the basis of radiation protection optimization design, and the accuracy of activation calculations depends on nuclear data. Based on the ENDF/B-VIII.0 and JEFF3.3 decay evaluation libraries, the influence of different nuclear data on the reactor structural material activation calculation is analyzed, and the nuclear data-related sensitivity and uncertainty quantification of radioactivity, decay heat and photon sources are carried out by the global sensitivity analysis method and the Latin Hypercube Sampling method. Based on uncertainty data in ENDF/B-VIII.0 and JEFF3.3, quantifying the uncertainty of radioactivity, decay heat and photon source in the shutdown dose calculation of reactor structural materials, the maximum uncertainty of radioactivity and decay heat reach 4.54 and 1.45%, respectively. The half-life and decay energy of 55Fe are the main sources of uncertainty.

Published in Frontiers in Energy Research

ISSN: 2296-598X (Online)
Publisher: Frontiers Media S.A.
Country of publisher: Switzerland
LCC subjects: General Works
Website: https://www.frontiersin.org/journals/energy-research

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