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非压水反应堆一种安全分级方法研究

Study on One Safety Classification Principle of Non-Pressurized Water Reactor
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摘要 物项的安全分级是核反应堆安全设计的基础和重要内容。考虑到反应堆各系统和设备对于核安全的重要程度不完全相同,设计中根据其承担的安全功能以及失效后果对反应堆建(构)筑物、系统和设备进行安全分级。随着我国核能科研和工程领域的发展,出现了多种类型的反应堆,其运行参数及系统设计与常规压水堆核电厂有很大区别,我国现有的针对压水堆制定的分级方法无法很好地适用于这类反应堆,导致了其安全分级存在一定困难。本文在分析现行HAD102/03和IAEA SSG-30物项分级方法的基础上,对SSG-30分级方法的思想和过程进行分析,并采用SSG-30的物项分级方法对典型池式反应堆进行安全分级,总结该方法在非常规压水堆上的应用特点,为此类型反应堆的物项分级提供指导。 The safety classification of items is the basis and important conponent of nuclear reactor safety design.Considering that the importance of reactor systems and equipment to nuclear safety is different,the safety classification of reactor buildings(structures),systems and equipment is carried out according to their safety functions and failure consequences.With the development of nuclear energy research and engineering in China,many reactors with innovative features are designed and constructed,their operating parameters and system design are very different from those of conventional PWR.The existing classification method for PWR in China cannot be well applied to these types of reactors,which leads to some difficulties in safety classification of these reactors.Based on the analysis of the current had 102/03 and IAEA SSG-30 item classification methods,this paper analyzes the principle and process of SSG-30 item classification method,and uses SSG-30 item classification method to carry out the safety classification of typical pool reactor.The classification method summarized in this paper can provides guidance for item classification of non-PWRs.
作者 孙微 张小伟 孙德泉 吴园园 SUN Wei;ZHANG Xiaowei;SUN Dequan;WU Yuanyuan(Nuclear and radiation safety center,Beijing 100082,China;Nuclear Technology Support Center,State Administration of Science,Technology and Industry for National Defense,Beijing 100080,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2022年第5期1146-1151,共6页 Nuclear Science and Engineering
关键词 非压水反应堆 安全分级 SSG-30 Non-PWR Safety classification SSG-30
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