超临界水冷堆热工水力与安全研发  

Research and Development on Thermal Hydraulic and Safety of Supercritical Water-cooled Reactor

作　　者：赵学斌 黄彦平[1] 臧金光[1] Zhao Xuebin;Huang Yanping;Zang Jinguang(CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu,610213,China)

机构地区：[1]中国核动力研究设计院中核核反应堆热工水力技术重点实验室,成都610213

出　　处：《核动力工程》2023年第5期223-231,共9页Nuclear Power Engineering

摘　　要：超临界水冷堆是第四代核能系统国际论坛确定的六种先进堆型中唯一的水冷堆。由于超临界水作为冷却剂以及超临界水在物理相态的特有属性,使其在热工水力方面有着独特的表现。本文介绍了超临界水冷堆热工水力的总体要求,描述了典型热工水力过程的基本特点及目前主要研发进展,着眼于超临界水冷堆工程提出了后续研发任务,以及未来超临界水冷堆的发展建议。Supercritical water cooled reactor(SCWR) is the only water-cooled reactor among the six advanced reactor types identified by the Generation IV International Forum.Supercritical water has a unique performance in thermal hydraulics due to its utilization as a coolant and unique properties in physical phase.This paper introduces the general requirements of SCWR thermal hydraulics,and describes the basic characteristics of typical thermal hydraulic processes and the main research and development progress at present.Focusing on the SCWR engineering application,this paper puts forward the follow-up research and development tasks and suggestions for future development of SCWR.

关 键 词：超临界水冷堆(SCWR) 热工水力 研发进展 研发任务 

分 类 号：TK124[动力工程及工程热物理—工程热物理] TL333[动力工程及工程热物理—热能工程]