Core cooling in pressurized-water reactor during water injection

Jun TAO; Jingxi LI; Lili TONG; Xuewu CAO

doi:10.13538/j.1001-8042/nst.22.60-64

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Core cooling in pressurized-water reactor during water injection

NUCLEAR ENGINEERING | Updated：2021-01-29

- Core cooling in pressurized-water reactor during water injection
- Nuclear Science and Techniques Vol. 22, Issue 1, (2011)
- Affiliations：
  
  1.School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
- Author bio：
  
  Corresponding author. E-mail address: caoxuewu@sjtu.edu.cn
  
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- Funds：
- DOI：10.13538/j.1001-8042/nst.22.60-64 CLC：
- Published：20 February 2011，
  
  Received：20 May 2010，
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Cite this article
Jun TAO, Jingxi LI, Lili TONG, et al. Core cooling in pressurized-water reactor during water injection. [J]. Nuclear Science and Techniques 22(1):60-64(2011)
DOI：

Jun TAO, Jingxi LI, Lili TONG, et al. Core cooling in pressurized-water reactor during water injection. [J]. Nuclear Science and Techniques 22(1):60-64(2011) DOI： 10.13538/j.1001-8042/nst.22.60-64.

Core cooling in pressurized-water reactor during water injection 1 first-author 1 1 1 corresp Corresponding author. E-mail address: caoxuewu@sjtu.edu.cn Corresponding author. E-mail address: caoxuewu@sjtu.edu.cn caoxuewu@sjtu.edu.cn School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China In this paper, the reactor core cooling and its melt progression terminating is evaluated, and the initiation criterion for reactor cavity flooding during water injection is determined. The core cooling in pressurized-water reactor of severe accident is simulated with the thermal hydraulic and severe accident code of SCDAP/RELAP5. The results show that the core melt progression is terminated by water injection, before the core debris has formed at bottom of core, and the initiation of reactor cavity flooding is indicated by the core exit temperature. Water injection Severe accident Severe accident management guideline Core damage state Cavity flooding PWR References U S NRC , Severe Accident Risks: An Assessment of Five U.S. Nuclear Power Plant, NUREG-1150 , Revision 1 , 1989 . Severe Accident Risks: An Assessment of Five U.S. Nuclear Power Dorsselaere J V , Fichot F . Nucl Eng Design . 2006 , 236 : 1976 - 1990 . Nucl Eng Design Idaho National Engineering Laboratory , Criteria for selecting important severe accident sequence, NRC 10CFR 5.0.54(f), Appendix 2, NUREG/CR-2300 , 1998 . Southern California Edison . Individual Plant Examination Report for San Onofre Nuclear Generating Station Units 2 and 3 , 1993, 1 : 40 - 51 . Individual Plant Examination Report for San Onofre Nuclear Generating Station Units 2 and 3 Omaha Public Power District Fort Calhoun Station . Individual Plant Examination Submittal , 1993 , 1 : 37 - 51 . Individual Plant Examination Submittal Knudson D L , Rempe J L . Nucl Eng Design , 2004 , 230 : 133 - 150 . Nucl Eng Design IAEA , Safety Standards: Severe Accident Management Programmes for Nuclear Power Plants. Safety Guide NO. N-S-G 2.15 , 2009 . Safety Standards: Severe Accident Management Programmes for Nuclear Power Plants. Safety Guide NO. N-S-G 2.15 Allison, C M . Nucl Eng Design , 2008 , 238 : 1547 - 1560 . Nucl Eng Design 10.13538/j.1001-8042/nst.22.60-64 Supported by National Basic Research Program of China (No.2009CB 724301) 2010-05-20 2011-02-20 2021-01-19 2011 Nuclear Science and Techniques 01 22

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