NUCLEAR TECHNIQUES, Volume. 47, Issue 12, 120601(2024)

Validation of the early in-vessel phenomenon analysis model of the severe accident analysis code MOSAP

Chao GUO1, Shihao WU2, Chuanqi ZHAO1, Yapei ZHANG2, Chao WEI1、*, and Yingwei WU2
Author Affiliations
  • 1Nuclear and Radiation Safety Center, Beijing 100082, China
  • 2Xi'an Jiaotong University, Xi'an 710049, China
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    References(17)

    [1] SU Guanghui[M]. Severe accident phenomenology of light water reactors(2016).

    [2] Wolf J R, Akers D W, Neimark I A. Relocation of molten material to the TMI-2 lower head[J]. Nuclear Safery, 35, 269-279(1994).

    [14] ZHANG Xuhao, WANG Hui, SHI Xueyao. Research on thermal hydraulic response inside containment based on integrated code[J]. Science & Technology Vision, 12-17(2022).

    [18] Hagen S, Hofmann P, Noack V et al. Results of SFD experiment CORA-13 (OECD international standard problem 31): KFK-5054[R](1993).

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    Chao GUO, Shihao WU, Chuanqi ZHAO, Yapei ZHANG, Chao WEI, Yingwei WU. Validation of the early in-vessel phenomenon analysis model of the severe accident analysis code MOSAP[J]. NUCLEAR TECHNIQUES, 2024, 47(12): 120601

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Feb. 26, 2024

    Accepted: --

    Published Online: Jan. 15, 2025

    The Author Email: WEI Chao (WEIChao)

    DOI:10.11889/j.0253-3219.2024.hjs.47.120601

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