国和一号关键核安全技术研发
Nuclear Safety Technology Development for CAP1400
郑明光 1汤搏 2严锦泉 1史国宝 1常华健 3曹克美 1匡波 4余凡 1王国栋 1张琨1
作者信息
- 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
- 折叠
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.
Abstract
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Key words
CAP 1400/passive safety/large advanced pressurized water reactor/high residual heat re-moval/in-vessel retention/radioactivity confinement引用本文复制引用
出版年
2024
国家科技期刊平台
NSTL
万方数据