The Research and Development Progress of SCWR

被引：0
|
作者：
Zang J. [1 ]
Huang Y. [1 ]
机构：
[1] Nuclear Power Institute of China, Chengdu
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2021年 / 42卷 / 06期
关键词：
R&D progress; SCWR; Suggestions and tasks;
D O I：
10.13832/j.jnpe.2021.06.0001
中图分类号：
O57 [原子核物理学、高能物理学];
学科分类号：
070202 ;
摘要：
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. © 2021, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
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页码：1 / 4
页数：3
相关论文
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