NUCLEAR TECHNIQUES, Volume. 46, Issue 1, 010601(2023)

Critical safety analysis method of spent fuel solution system

Huabei YIN1, Yongping WANG1、*, Junli GOU1, Guoming LIU2, Tiejun ZU1, Wen YIN1, Youqi ZHENG1, and Xianan DU1
Author Affiliations
  • 1Xi'an Jiaotong University, Xi'an 710049, China
  • 2China Nuclear Power Engineering Co., Ltd., Beijing 100840, China
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    [2] Nakajima K, Yamane Y, Ogawa K et al. TRACY transient experiment databook. 1) pulse withdrawal experiment[R]. Japan Atomic Energy Research Institute(2002).

    [3] Yamane Y, Nakajima K, Yamamoto T et al. Development of criticality accident analysis code AGNES[R]. Japan Atomic Energy Research Institute(2003).

    [4] Basoglu B, Yamamoto T, Okuno H et al. Development of a new simulation code for evaluation of criticality transients involving fissile solution boiling[R]. Japan Atomic Energy Research Institute(1998).

    [7] WANG Liangzi. Physics calculation model based on Monte Carlo method and characteristics analysis of aqueous homogeneous reactors[D](2011).

    [10] Dulla S, Mund E H, Ravetto P. Accuracy of a predictor-corrector quasi-static method for space-time reactor dynamics[C](2006).

    [13] Lane J A, MacPherson H G, Maslan F. Fluid fuel reactors: molten salt reactors, aqueous homogeneous reactors, fluoride reactors, chloride reactors, liquid metal reactors and why liquid fission[M]. V20181227c(2018).

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    Huabei YIN, Yongping WANG, Junli GOU, Guoming LIU, Tiejun ZU, Wen YIN, Youqi ZHENG, Xianan DU. Critical safety analysis method of spent fuel solution system[J]. NUCLEAR TECHNIQUES, 2023, 46(1): 010601

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    Paper Information

    Category: Research Articles

    Received: Apr. 20, 2022

    Accepted: --

    Published Online: Feb. 17, 2023

    The Author Email: WANG Yongping (wangyongping0627@xjtu.edu.cn)

    DOI:10.11889/j.0253-3219.2023.hjs.46.010601

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