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核电厂严重事故管理要求在“华龙一号”设计中的应用 被引量:1

Application of Nuclear Power Plant Severe Accident Management Requirements in HPR1000 Design
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摘要 "华龙一号"是我国自主研发的三代核电机组,其设计应满足最新的核安全法规标准要求。在国际国内最新核安全法规标准中,针对核电厂应对严重事故措施的设计均提出了明确的要求。在发生严重事故的情况下,核电厂应设置完善的严重事故缓解措施,以防止大量放射性物质的释放。为确保"华龙一号"严重事故应对措施设计满足最新核安全法规标准中的相关要求,在"华龙一号"设计中,从严重事故管理要求的角度出发,结合"华龙一号"的严重事故管理总体策略,提出了严重事故缓解措施设计的功能要求、可用性要求、可达性要求、支持系统设计要求等一系列设计要求。这些要求的实现最终显著提高了"华龙一号"应对严重事故能力,并为"华龙一号"安全目标的最终实现提供了充分的保障。 As generation III nuclear power plant developed by China, HPR1000 should satisfy the requirement of the latest nuclear safety codes and standards. In the latest national and international nuclear safety codes and standards, explicit requirements have been given for the design of severe accident management measures. Severe accident mitigation measures in the plant should be designed so as to prevent large radiological releases. In order to assure that HPR1000's design of severe accident mitigating measures can satisfy the latest nuclear safety codes and standards, from the perspective of severe accident management requirements, detailed design requirements on the functionality, usability, accessibility, and supporting system design of severe accident mitigation measures have been suggested for HPR1000, based on the overall strategies of HPR1000 severe accident management. By realizing the above design requirement, HPR1000's ability to cope with severe accident threat has been substantially improved, and sufficient assurance has been provided for the final satisfaction of HPR1000's safety goal.
出处 《中国核电》 2017年第4期489-493,共5页 China Nuclear Power
关键词 严重事故管理 “华龙一号” 设计要求 severe accident management HPR1000 design requirements
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