百万千瓦级核电站轴封型主泵整机集成试验验证优化方案研究  

Reserch of Optimal Integrated Verification Test Program for Shaft Seal Reactor Coolant Pump of 1000 MW Nuclear Power Plant

作　　者：陈兴江 彭放[2] 丛国辉 符伟[3] 罗志远 Chen Xingjiang;Peng Fang;Cong Guohui;Fu Wei;Luo Zhiyuan(State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment,China Nuclear Power Engineering Co.Ltd.,Shenzhen,Guangdong,518172,China;Nuclear Power Institute of China,Chengdu,610213,China;Shenyang Blower Works Group Corporation,Shenyang,110869,China)

机构地区：[1]中广核工程有限公司核电安全监控技术与装备国家重点实验室,广东深圳518172 [2]中国核动力研究设计院,成都610213 [3]沈阳鼓风机集团股份有限公司,沈阳110869

出　　处：《核动力工程》2020年第1期113-116,共4页Nuclear Power Engineering

基　　金：国家科技支撑计划项目(2015BAA08B01,2015BAA08B02,2015BAA08B03);广东省科技计划项目(2015B090901040)。

摘　　要：为确保主泵的安全性和可靠性,主泵整机在完成集成设计后需通过试验进行验证。文中介绍了主泵设计与验证的总体思路,提出了主泵工程样机需开展的整机试验项目。基于已有的试验条件,进行了主泵整机集成试验验证方案的优化和可行性分析。分析结果表明,在充分开展主泵各模块、子模块、部件和材料的试验与分析的基础上,可采用小流量试验方案进行主泵整机集成试验验证。In order to ensure the safety and reliability of the reactor coolant pump, the integrated design needs to be verified by experiments. The general idea of the design and verification of the reactor coolant pump and the test items for the engineering prototype of the reactor coolant pump are introduced in this paper. The optimal integrated verification test program of the reactor coolant pump is provided and the feasibility of the test program is analyzed. The results show that the integrated verification test for the reactor coolant pump can be achieved by using the small flow test based on the test and analysis of the modules, sub-modules, components and materials of the reactor coolant pump.

关 键 词：主泵 集成设计 整机试验 可行性 

分 类 号：TM623[电气工程—电力系统及自动化]