核主泵内部流动研究现状与技术发展综述

核主泵是反应堆冷却剂系统中唯一高速旋转设备,是影响核电厂安全性和可靠性的最关键设备,其长时间高效、稳定、安全地运行对防止核电厂事故的发生极为重要.近年来,随着全球核电工业高速发展,核主泵的重要性引起广泛关注.核主泵作为一回路承压边界的重要组成部分,在启停、地震、海啸等瞬态和异常工况下,或发生卡轴、轴密封泄漏以及失去外动力等事故时,核主泵驱动冷却剂的循环能力与反应堆释热之间的平衡遭到破坏,严重威胁堆芯安全.各种复杂工况下核主泵关键部件及其关联系统的复杂性和高安全性,是核主泵设计和制造难度极高的主要原因.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.

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

The reactor coolant pump is the only high-speed rotating equipment in the reactor coolant system. It is the most critical equipment affecting the safety and reliability of nuclear power plants.Its long-term efficient, stable and safe operation is extremely important to prevent nuclear power plant accidents. In recent years, with the rapid development of the global nuclear power industry, the importance of the reactor coolant pump has attracted widespread attention. The reactor coolant pump is a component of the pressure boundary of the primary circuit. Under transient and catastrophic extreme conditions such as start and stop, earthquake, or tsunami such as shaft jamming, shaft seal leakage or loss of external power, the balance between the reactor coolant pump cooling capacity and heat released from the reactor is disrupted, seriously threatening the safety of the reactorcore. The complexity and high safety of the key components of the reactor coolant pump and its associated systems under various complex working conditions are the main reasons for the extreme difficulty in manufactu-ring the reactor coolant pump. 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-structure coupling, etc.The safety and reliability of the reactor coolant pump are extremely important, but the design, processing and ma-nufacturing 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.