邹树梁,李书帆.基于核电设计准则的AP1000与高温气冷堆核电技术安全性比较研究[J].,2018,(5):5-9
基于核电设计准则的AP1000与高温气冷堆核电技术安全性比较研究
Comparison of Safety Analysis in AP1000 and HTGR Based on Nuclear Power Design Criteria
投稿时间:2018-03-14  
DOI:
中文关键词:  AP1000  四代核电  安全设计  固有安全性
English Keywords:AP1000  GenerationⅣ nuclear power  safety design  inherent safety
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作者单位
邹树梁 南华大学 核设施应急安全作业技术与装备湖南省重点实验室,湖南 衡阳 421000 
李书帆 南华大学 核设施应急安全作业技术与装备湖南省重点实验室,湖南 衡阳 421000 
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中文摘要:
      简述我国三代及四代核电技术的几种类型,三代核电以AP1000为主,阐述其非能动安全性。四代核电以高温气冷堆为主,并总结它们的发展历程、相关关系和技术特点。基于核电设计准则,对比AP1000、高温气冷堆、钠冷快堆部分参数,探究四代核电技术新增固有安全性的几种主要表现形式。通过比较研究得出,在安全特性上四代核电技术固有安全性更为突出,在材料特性、结构特性上等都有了显著提高。
English Summary:
      This paper briefly describes several types of generationⅢ and generationⅣ reactor in our country.The GenⅢ is mainly in AP1000 and elaboration of its passive safety.The GenⅣ is mainly in HTGR and their development history, related relations and technical characteristics are summarized.Based on the nuclear power design criteria, some parameters of AP 1000, HTGR and sodium cooled fast reactor are compared, and several main manifestations of new inherent safety of GenⅣ are explored.In sum by comparison:In terms of safety characteristics, the inherent safety of the GenⅣ nuclear power technology will be more prominent and its material /structural characteristics have been significantly improved .
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