国外超临界轻水反应堆研究  

Foreign Study of Super Critical Light Water Cooled Reactor

作　　者：刘松涛[1] 张森如[1] 张虹[1] 

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

出　　处：《东方电气评论》2005年第2期69-74,79,共7页Dongfang Electric Review

摘　　要：超临界水冷却反应堆(SCLWR-H)系统是一种高温高压的水冷反应堆,它可以在高于水的热力学临界点(374℃,22.1MPa)的工况下运行。超临界的水冷却剂可以使系统的热效率比目前的轻水反应堆高出大约1/3,同时由于冷却剂在反应堆内不改变相态并且直接与能量转换设备相连,这可以显著简化装置的配置。Super critical light water cooled reactor(SCWR) is a high temperature ,high pressure water cooled reactor,which can operate above the state of the thermodynamic critical point of water(374 ℃,22.1 MPa).The big advantage of the SCWR concept is that the temperatures of major components are within the temperatures of the components of LWR and supercritical FPP.The experience of these components of LWR and supercritical fossil fired power plants will be fully utilized for SCWR.The effciency of the coolant under super critical state is 1/3 greater than that of the normal light water reactor.And the equipments of SCWR are also simpler.

关 键 词：超临界 轻水冷却 第四代核能系统 GIF 

分 类 号：TL421[核科学技术—核技术及应用]