超临界水冷堆开发现状与前景展望  

Development Status and Application Prospect of Supercritical-Pressure Light Water Cooled Reactor

作　　者：李满昌[1] 王明利[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术国家级重点实验室,成都610041

出　　处：《核动力工程》2006年第2期1-4,44,共5页Nuclear Power Engineering

摘　　要：超临界水冷堆是被国际上选定为第四代核能系统长远开发的6种堆型之一,是在现有LWR和超临界火电技术基础上发展起来的革新型设计。在技术上,超临界水冷堆可以借鉴现有PWR和超临界火电的设计、建造和运行经验,不存在不可逾越的技术障碍。我国近期和中期目标都是采用压水堆技术,考虑到技术的继承性和可持续发展的要求,开发和研制超临界水冷堆核能系统是必然的选择。The Supercritical-pressure Light Water Cooled Reactor （SCWR） is selected by the Generation Ⅳ International Forum （GIF） as one of the six Generation IV nuclear systems that will be developed in the future, and it is an innovative design based on the existing technologies used in LWR and supercritical coal-fired plants. Technically, SCWR may be based on the design, construction and operation experiences in existing PWR and supercritical coal-fired plants, which means that there is no insolvable technology difficultties. Since PWR technology will be adopted in the near term and medium term projects in China, and considering the sustainable development of the technology, it is an inevitable choice to research and develop the nuclear system of supercritical light water cooled reactor.

关 键 词：超临界水冷堆 开发现状 前景分析 

分 类 号：TL4[核科学技术—核技术及应用]