Chinese Journal of Ship Research, Volume. 18, Issue 3, 231(2023)

Level 1 probabilistic safety analysis of internal event in marine nuclear power plants

Shuai WANG1, Feiyun DENG2, and Junxin WANG1
Author Affiliations
  • 1China Ship Development and Design Center, Wuhan 430064, China
  • 2Shanghai First Military Representative Office, Naval Armament Department of PLAN, Shanghai 201913, China
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    References(7)

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    [8] [8] International Atomic Energy Agency. Defining initiating events f purposes of probabilistic safety assessment[M]. Vienna: IAEA , 1993.

    [9] [9] SWAIN A D, GUTTMANN H E. Hbook of humanreliability analysis with emphasis on nuclear power plant applications. Final rept[R]. United States: U. S. Nuclear Regulaty Commission, 1983.

    [10] [10] GERTMAN D, BLACKMAN H, MARBLE J, et al. The SPARH human reliability analysis method (NUREGCR6883) [R]. Washington D. C. : U. S. Nuclear Regulaty Commission, 2005.

    [11] [11] RAUS M. Common‐cause failures[M]. Hoboken, USA: John Wiley & Sons, Inc. , 2014: 309342.

    [12] [12] EIDE S A, CHMIELEWSKI S V, SWANTZ T D. Generic, component failure data base f light water liquid sodium react PRAs[R]. Washington D. C. : United States Department of Energy, 1990.

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    Shuai WANG, Feiyun DENG, Junxin WANG. Level 1 probabilistic safety analysis of internal event in marine nuclear power plants[J]. Chinese Journal of Ship Research, 2023, 18(3): 231

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    Paper Information

    Category: Marine Machinery, Electrical Equipment and Automation

    Received: Jul. 29, 2021

    Accepted: --

    Published Online: Mar. 20, 2025

    The Author Email:

    DOI:10.19693/j.issn.1673-3185.02468

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