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运行核电厂事故管理若干问题的探讨 被引量:3

Discussion on Several Issues of the Accidents Management of Nuclear Power Plants in Operation
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摘要 本文就运行核电厂事故管理的必要性、实施原则及事故管理大纲等问题进行了探讨。本文认为,为了在超设计基准事故发展过程中进行事故管理,应制定和实施核电厂事故管理大纲,使事故管理所需要的所有物项都处在备用状态,以便需要时进行有效地事故管理。 This article discusses several issues of the accident management of nuclear power plants in operation, for example: the necessity, implementation principle of accident management and accident management program etc. For conducting accident management for beyond design basis accidents, this article thinks that the accident management program should be developed and implemented to ensure that the plant and its personnel with responsibilities for accident management are adequately prepared to take effective on-site actions to prevent or mitigate the consequences of severe accident.
出处 《核安全》 2009年第2期14-18,24,共6页 Nuclear Safety
关键词 核电厂 超设计基准事故 事故管理 nuclear power plant beyond design basis accident accident management
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  • 1.NRC AP-1000 FSER,19.1.2 Special Advanced Design Features[]..
  • 2.AP-1000 FSAR-6.3.2.2.8.5 Automatic Depressurization Valves[]..
  • 3.AP-1000 FSAR-5.2 Integrity of Reactor Coolant Pressure Boundary[]..
  • 4.AP-1000 FSAR-5.4.6 Automatic Depressurization System Valves[]..
  • 5.AP-1000 PSA-CHAPTER 11 PASSIVE COOLING SYSTEM- AUTOMATIC DEPRESSURIZATION SYSTEM[]..
  • 6.AP-1000 PSA-34.2.1 In-Vessel Retention of Molten Core Debris[]..
  • 7.AP-1000 PSA-CHAPTER 39 IN-VESSEL RETENTION OF MOLTEN CORE DEBRIS[]..
  • 8.AP-1000 FSAR-5.3.5 Reactor Vessel Insulation[]..
  • 9.AP-1000 FSAR-6.3.2.1.3 Safety Injection During Loss of Coolant Accidents[]..
  • 10.AP-1000 FSAR-6.2.4 Containment Hydrogen Control System[]..

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