国和一号关键核安全技术研发  

Nuclear Safety Technology Development for CAP1400

作　　者：郑明光[1] 汤搏 严锦泉[1] 史国宝[1] 常华健 曹克美[1] 匡波[4] 余凡[1] 王国栋[1] 张琨[1] ZHENG Mingguang;TANG Bo;YAN Jinquan;SHI Guobao;CHANG Huajian;CAO Kemei;KUANG Bo;YU Fan;WANG Guodong;ZHANG Kun(Shanghai Nuclear Engineering Research&Design Institute Co.,Ltd.,Shanghai 200233,China;Nuclear and Radiation Safety Center,Ministry of Ecology and Environment,Beijing 102401,China;State Nuclear Power Technology R&D Center,Beijing 100190,China;Shanghai Jiao Tong University,Shanghai 200240,China)

机构地区：[1]上海核工程研究设计院股份有限公司,上海200233 [2]生态环境部核与辐射安全中心,北京102401 [3]国家核电技术有限公司北京研发中心,北京100190 [4]上海交通大学,上海200240

出　　处：《原子能科学技术》2024年第S02期355-361,共7页Atomic Energy Science and Technology

摘　　要：基于当前各类能源技术基础和核电技术发展水平判断,核能是社会清洁低碳转型与可持续发展的重要支撑,高安全高可靠性的大型先进压水堆核电机组是未来30年内的主力机型。本文围绕大型先进压水堆核电站国家科技重大专项所面临的重大挑战,主要阐述了通过解决“高功率核燃料冷却难”“超高温熔融物滞留难”和“高温高压高放射性包容难”三大关键技术难题,来保证从设计上消除大规模放射性释放可能性或进一步降低核电批量化建设的核安全风险。Based on the current energy technology and technical development of nuclear power,nuclear energy is indispensable for the energy transformation for clean,low-carbon and sustainable development,and the large advanced pressurized water reactor with high safety and reliability would be the main support of energy development in the next 30 years.Facing the challenges in the National Science and Technology Key Project for large advanced pressurized water reactor,this paper states how to resolve three critical problems such as the high residual heat removal,core melt retention and radioactivity confinements thus to ensure the elimination of significant release of radioactivity or to reduce the nuclear safety risks at design stage for the mass construction of nuclear power plants.

关 键 词：国和一号 非能动安全 大型先进压水堆 高余热导出 熔融物堆内滞留 放射性包容 

分 类 号：TL334[核科学技术—核技术及应用]