超临界水堆堆芯和燃料组件概念综述  

Introduction to the Design Conception of SCWR Core and Fuel Assembly

作　　者：史国宝[1] 赵冬建[1] 廖承奎[1] 司胜义[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核电工程与技术》2008年第2期38-48,共11页Nuclear Power Engineering and Technology

基　　金：973计划（2007CB209800）

摘　　要：超临界水堆作为六种第四代未来堆型中唯一的水冷堆，受到广泛重视。尽管超临界水堆的创新设计可大量利用压水堆和沸水堆已积累的技术储备，并可利用超临界火电站的技术，但仍有大量的研究开发工作有待于开展。本文主要针对热中子谱超临界水堆及其燃料纽件的设计概念进行综述，并对设计的出发点、关注点作了说明。Supercritical Water Cooled Reactor （SCWR）, regarded as one of the promising future Generation IV reactors, has achieved significant interests of nuclear industries and institutes. Besides the utilization of the accumulated technology of the light water reactor and supercritical fossil power plant, extensive R ＆ D activities should be carried out for the innovative design of SCWR. The main design concepts of SCWR core and fuel assembly, especially of thermal-spectrum SCWR, are described in this paper, and a few comments are provided for the key points of the design.

关 键 词：超临界水堆 堆芯 燃料组件 设计概念 

分 类 号：TL351.1[核科学技术—核技术及应用] TL352