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Analysis of hot leg natural circulation under station blackout severe accident 被引量:2

Analysis of hot leg natural circulation under station blackout severe accident
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摘要 Under severe accidents, natural circulation flows are important to influence the accident progression and result in a pressurized water reactor (PWR). In a station blackout accident with no recovery of steam generator (SG) auxiliary feedwater (TMLB' severe accident scenario), the hot leg countercurrent natural circulation flow is analyzed by using a severe-accident code, to better understand its potential impacts on the creep-rupture timing among the surge line, the hot leg, and SG tubes. The results show that the natural circulation may delay the failure time of the hot leg. The recirculation ratio and the hot mixing factor are also calculated and discussed. Under severe accidents, natural circulation flows are important to influence the accident progression and result in a pressurized water reactor (PWR). In a station blackout accident with no recovery of steam generator (SG) auxiliary feedwater (TMLB' severe accident scenario), the hot leg countercurrent natural circulation flow is analyzed by using a severe-accident code, to better understand its potential impacts on the creep-rupture timing among the surge line, the hot leg, and SG tubes. The results show that the natural circulation may delay the failure time of the hot leg. The recirculation ratio and the hot mixing factor are also calculated and discussed.
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 2007年第2期123-128,共6页 核技术(英文)
关键词 压水堆 全场断电 严重事故 热管段 自然循环 Severe accident, TMLB' accident, Natural circulation, Hot leg countercurrent flow
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参考文献8

  • 1Idaho National Engineering Laboratory. Severe Accident National Circulation Studies at the INEL, U.S. Nuclear Regulatory Commission, NUREG/CR-6285, 1994.
  • 2Fuller E L, Kenton M A, Epstein M, et al. Risk from severe accidents involving steam generator tube leaks or ruptures, Electric Power Research Institute, EPRI TR-106194, 1995.
  • 3Paul Scherrer Institut. Implementation of severe accident management measures, OECD Nuclear Energy Agency, NEA/CSNI/R (2001) 20, 2001.
  • 4Fauske and Associate, Inc. MAAP4 User's Manual. Electric Power Research Institute, Electric Power Research Institute, EPRI Research Project 3131-02, 1994.
  • 5SGTR Severe Accident Working Group. Risk assessment of severe accident-induced steam generator tube rupture, U.S. Nuclear Regulatory Commission, NUREG-1570, 1998.
  • 6Boyd C F, Hardesty K. Analysis of 1/7 scale steam generator inlet plenum mixing during a PWR severe accident, U.S. Nuclear Regulatory Commission, NUREG-1781, 2003.
  • 7Boyd C F, Helton D M. Hardesty K. Analysis of full scale steam generator inlet plenum mixing during a PWR severe accident, U.S. Nuclear Regulatory Commission, NUREG-1788, 2004.
  • 8Liao Y, Vierow K. Nuclear Technology, 2005, 152(3): 302-313.

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