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CLC number: TL36

On-line Access: 2016-11-03

Received: 2016-01-26

Revision Accepted: 2016-09-28

Crosschecked: 2016-10-10

Cited: 0

Clicked: 3038

Citations:  Bibtex RefMan EndNote GB/T7714

 ORCID:

Ji-en Ma

http://orcid.org/0000-0001-6970-3634

Yong Wang

http://orcid.org/0000-0003-1870-9547

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Journal of Zhejiang University SCIENCE A 2016 Vol.17 No.11 P.911-922

http://doi.org/10.1631/jzus.A1600035


Generation III pressurized water reactors and China’s nuclear power


Author(s):  Yong Wang, Ji-en Ma, You-tong Fang

Affiliation(s):  Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China; more

Corresponding email(s):   majien@zju.edu.cn

Key Words:  Generation III (GIII) pressurized water reactor (PWR), Performance, Safety, Economy, Nuclear power


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Yong Wang, Ji-en Ma, You-tong Fang. Generation III pressurized water reactors and China’s nuclear power[J]. Journal of Zhejiang University Science A, 2016, 17(11): 911-922.

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Abstract: 
The design philosophy, overall performance, safety, and economy of three typical generation III (GIII) pressurized water reactors, EPR, AES2006, and CAP1400, are analyzed comprehensively in this paper. Based on comparison with and the lessons learned from the Fukushima nuclear accident, we forecast a future reactor for China’s commercial nuclear power plant. Moreover, we put forward important technological fields of GIII nuclear power plants to which attention should be paid, including the enhancement of defense in depth, defense against extreme external events, severe accident mitigation, design simplification and standardization, improvement in economic competitiveness, load following capability, and adaptation to climate change.

世界三代压水堆主要机型技术分析

概要:本文针对目前主要的第三代压水堆机型EPR、AES2006以及CAP1400,从核电厂设计理念,综合性能、安全性和经济性等方面进行对比分析。在此基础上,结合福岛核事故,探讨中国商用核电未来的技术发展方向。通过对EPR、AES2006以及CAP1400的对比分析发现,尽管它们采用了不同的设计理念和技术方式,但作为目前第三代商用压水堆的代表机型,其目标都在于提高核电厂的整体性能、安全性能和经济性,从而在提高安全性的前提下,强化其相比于其他发电方式的竞争力,获得政府、公众和业主的支持。第三代压水堆技术的主要努力方向在于:在安全方面,进一步强化纵深防御体系,将设计加强工况(包括全厂断电、商用飞机撞击和预期未能停堆的瞬态等)纳入设计考虑的范畴;设置预防和缓解严重事故的措施;考虑极端外部事件设防(包括地震和洪水等)。再者,对非能动安全与能动安全两者之间的关系定位、相互衔接进行优化设置,从而更好的保障核安全。此外,严重事故下设备和仪表的可用性成为福岛核事故后需要特别关注的问题。从经济性的角度讲,加强设计简化和标准化,及时将EPR、AES2006以及CAP1400的首台组的建造经验反馈到后续机组,改进可建造性和模块化从而确保经济性和缩短建造周期。从运行的角度讲,考虑国内核电装机容量的增加、较长的设计寿命以及其他可再生能源的并网,核电设计需强化负荷跟踪的能力。长期来看,需要考虑可能的气候变化,从而确保核电站(沿海和内陆)具有较强的应对极端气候以及较高环境温度和冷却水升温的能力。
关键词:第三代压水堆技术;性能;安全性;经济性;核电

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