The Research and Development Progress of SCWR
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摘要: 超临界水冷堆（SCWR）是第四代核能系统国际论坛（GIF）确定的6种堆型中唯一的水冷堆。本文描述了SCWR的技术特点，回顾了我国SCWR的研发历程，简要梳理了国际上加拿大、欧盟、日本等在SCWR方面的最新研发情况。最后，本文总结了SCWR的技术优势、面临的技术挑战和发展机遇。
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关键词:
- 超临界水冷堆（SCWR） /
- 研发进展 /
- 建议和任务
Abstract: Supercritical water cooled reactor (SCWR) is the only water-cooled reactor among the six types of reactors identified by the Generation IV International Forum. This paper describes the technical characteristics of SCWR, reviews the research and development (R&D) process of SCWR in China, and briefly reviews the latest R&D developments of SCWR in Canada, EU, Japan and other countries. Finally, this paper summarizes the technical advantages, technical challenges and development opportunities of SCWR.-
Key words:
- SCWR /
- R&D progress /
- Suggestions and tasks
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[1] GIF Group. A technology roadmap for generation IV nuclear energy systems: GIF-002-00[R]. US: the US DOE Nuclear Energy Research Advisory Committee and the Generation Ⅳ International Forum, 2002. [2] KELLY J E. Generation IV international forum: a decade of progress through international cooperation[J]. Progress in Nuclear Energy, 2014(77): 240-246. doi: 10.1016/j.pnucene.2014.02.010 [3] 黄彦平,臧金光. 超临界水冷堆[J]. 现代物理知识,2018, 30(4): 19-24. [4] SCWR System Steering Committee. Status report on supercritical water-cooled reactors[C]. 48th GIF PG and 42nd EG Meeting. Weihai, 2019 [5] 周之入,黄彦平,臧金光,等. 超临界水冷堆系统国际研发动态与启示[J]. 核动力工程,2016, 37(1): 162-166. [6] SCHULENBERG T, LEUNG L. Super-critical water-cooled reactors[M]. PIORO I L. Handbook of Generation IV Nuclear Reactors. Britain: Woodhead Publishing, 2016: 189-220 -
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