核主泵内部流动研究现状与技术发展综述

Review on research status of internal flow and technological development of reactor coolant pump

针对核电技术的发展历程开展论述,介绍世界主要三代核电技术和中国三代核电建设和发展现状,介绍了中国独立自主三代核电技术“华龙一号”HPR1000和“国和一号”CAP1400,并以CAP系列核主泵为例简要介绍第三代压水堆系统和关键设备,介绍了2种典型无轴密封形式的核主泵:屏蔽电机核主泵和湿绕组核主泵.针对核主泵的水力优化设计、全特性、事故工况下水动力特性、气液两相流动、空化特性、流固耦合等内部流动研究现状开展论述.核主泵的安全可靠极为重要,核主泵设计加工制造也极具挑战.因此对核主泵内部流动基础理论和关键技术进行深入研究,突破国外的技术壁垒,掌握自主知识产权的核心技术和关键技术,实现核主泵技术的跨越式发展,是当前中国急待解决的“卡脖子”难题.

Firstly,the development history of nuclear power technology is discussed,then the world′s main third-generation nuclear power technologies and the current status of China third-generation nuclear power construction and development is followed.Specially,China own third-generation technology,such as Hualong No.1—HPR1000 and Guohe No.1—CAP1400 reactor coolant pumps is described.Further,and the third-generation pressurized water reactor system and key equipment explained briefly using the CAP reactor coolant pumpseries as an example.Two typical shaft sealless pumps:canned motor reactor coolant pump and wet winding reactor coolant pump are introduced.The current research status of internal flow of the reactor coolant pump is presented,including hydraulic optimization design,complete characteristics,hydraulic performance under accident conditions,gas-liquid two-phase flow,cavitation characteristics,fluid-solid interaction,etc.The safety and reliability of the reactor coolant pump are extremely important,but the design,processing and manufacturing of the pump are also quite challenging.Therefore,in-depth investigation into the basic theory of internal flow and key technology of the reactor coolant pump,breaking through foreign technical barriers,mastering the core and key technologies with own intellectual property rights,and realizing the leap-forward development in reactor coolant pump technology are current stranglehold problems that China needs to solve urgently.