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A9-1000严重事故缓解措施 被引量:6

AP-1000 Severe Accident Mitigation Feature
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摘要 本文简介了AP-1000严重事故主要缓解措施,包括自动卸压(ADS)系统、熔融物堆内保持(IVR)系统、氢气控制系统、严重事故下余热排除系统和事故管理等。 This article briefly presents AP-1000 main mitigation features for severe accident, including the automatic depressurization system(ADS),the in-vessel retention(IVR) of molten core debris, the containment hydrogen control system, the passive containment cooling system(PCS), the accident management etc .
作者 张英振
出处 《核安全》 2007年第2期38-45,共8页 Nuclear Safety
关键词 核电厂 严重事故 缓解措施 nuclear power plant severe accident mitigation feature
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参考文献10

  • 1.NRC AP-1000 FSER,19.1.2 Special Advanced Design Features[].. 被引量:1
  • 2.AP-1000 FSAR-6.3.2.2.8.5 Automatic Depressurization Valves[].. 被引量:1
  • 3.AP-1000 FSAR-5.2 Integrity of Reactor Coolant Pressure Boundary[].. 被引量:1
  • 4.AP-1000 FSAR-5.4.6 Automatic Depressurization System Valves[].. 被引量:1
  • 5.AP-1000 PSA-CHAPTER 11 PASSIVE COOLING SYSTEM- AUTOMATIC DEPRESSURIZATION SYSTEM[].. 被引量:1
  • 6.AP-1000 PSA-34.2.1 In-Vessel Retention of Molten Core Debris[].. 被引量:1
  • 7.AP-1000 PSA-CHAPTER 39 IN-VESSEL RETENTION OF MOLTEN CORE DEBRIS[].. 被引量:1
  • 8.AP-1000 FSAR-5.3.5 Reactor Vessel Insulation[].. 被引量:1
  • 9.AP-1000 FSAR-6.3.2.1.3 Safety Injection During Loss of Coolant Accidents[].. 被引量:1
  • 10.AP-1000 FSAR-6.2.4 Containment Hydrogen Control System[].. 被引量:1

同被引文献46

  • 1舒睿,许川.秦山核电二期工程严重事故研究[J].核动力工程,2003,24(z1):36-39. 被引量:7
  • 2Hoch.,LE,陈世君.AP600非能动堆芯事故冷却系统整体试验[J].国外核动力,1996,17(2):1-13. 被引量:2
  • 3V Asmolov, N N Ponomarev-Stepony, V Strizhov, et al. Challenges Left in the Area of In-vessel Melt Retention [ J ]. Nuclear Engineering and Design ,2001 (209) : 87 - 96. 被引量:1
  • 4Rempe J L,Knudson D L,Allison C M,et al. Potential for AP600 In-vessel Retention Through Ex-vessel Flooding [ R ]. ID Idaho: Idaho National Engineering and Environ- mental Laboratory, 1997. 被引量:1
  • 5Hawkes G L, O' Brien J E. ARSAP AP600 In-vessel Coolability Thermal Analysis, Final Report [ R ]. Washing- ton, D. C. : DOFJID - 10369,1991. 被引量:1
  • 6Hammersley, R J, Henry, R E, et al. In-vessel Retention for the AP600 Design During Severe Accidents [ C ]//Presented at the Second Intern, Conference on Nuclear Engineering ( ICONE - 2). San Francisco : ICONE, 1993. 被引量:1
  • 7Bal T Ral Sehgal. Stabilization and Termination of Servere Accidents in LWRs [ J ]. Nuclear Engineering and Design, 2006(236) : 1941 - 1952. 被引量:1
  • 8Theofanous T G, Liu C, Assition S, et al. In-vessel Coolabil- ity and Retention of a Core Melt [ J ]. Nuclear Engineering and Design, 1997 (169) : 1 - 48. 被引量:1
  • 9林诚格.非能动安全核电厂AP1000[M].北京:原子能出版社,2008. 被引量:1
  • 10AREVA. Taishan Nuclear Power Plant Preliminary Safety Analysis Report [ R ]. Taishan: Taishan Nuclear Power Company Limited ,2008. 被引量:1

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