2016年 第2卷 第1期
《工程（英文）》 >> 2016年 第2卷 第1期 doi: 10.1016/J.ENG.2016.01.018
CAP1400 的总体设计和技术创新
Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
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摘要
压水堆CAP1400是基于中国核工业研发体系和装备制造能力以及非能动压水堆AP1000 的引进和消化吸收，并经过集成创新与再创新而形成的具有自主知识产权的第三代非能动先进压水堆核电型号。本文通过对CAP1400的总体设计思路、主要性能指标和技术参数、电站安全设计，以及在安全性、经济性和先进性等方面的阐述，论述了CAP1400作为第三代压水堆堆型的技术内涵和技术创新。此外，作为国家科技重大专项的成果，CAP1400型号的研发促进了中国自主核电在研发设计、试验和设备制造水平方面的整体提升，实现了核电设计与装备技术由第二代到第三代的升级。
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参考文献
[ 1 ] EPRI ANT. Advanced Light Water Reactor Utility Requirements Document, revision 12, 3002000507. Palo Alto: Electric Power Research Institute; 2013.
[ 2 ] Schulz TL. Westinghouse AP1000 advanced passive plant. Nucl Eng Des 2006; 236(14−16): 1547−57. 链接1
[ 3 ] Lin CG. An advanced passive plant AP1000. Beijing: Atomic Energy Press; 2008. Chinese.
[ 4 ] EPRI ANT. EPRI Utility Requirements Document (URD) Fukushima lessons-learned treatment, 3002002074. Palo Alto: Electric Power Research Institute; 2013.
[ 5 ] National Nuclear Safety Administration. General technology requirements for nuclear power plants after Fukushima Accidents (trial implementation). Beijing: National Nuclear Safety Administration; 2012. Chinese.
[ 6 ] Preliminary safety analysis report of CAP1400 demonstration project. Shanghai: Shanghai Nuclear Engineering Research and Design Institute; 2014Oct.
[ 7 ] Liu CY, Bi GW, Yang B. Preliminary study on core design with 50% MOX fuel in PWRs. Nucl Sci Eng 2015; 35(2): 314−9. Chinese.
[ 8 ] Cheng SJ, Wang XW, Ge HH, Xia ZF. Analysis of a large wide-body commercial plane impact on CAP1400 shield building. In: Liu X, Ang A, editors Sustainable Development of Critical Infrastructure; 2014May16−18; Shanghai, China. Reston: American Society of Civil Engineers; 2014. p. 338−46.
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