压水堆核电站一回路工况变化对主泵主要机械性能的影响  

Effect of Operation Conditions of Primary Coolant System of PWR NPP on Mechanic Performance of Primary Coolant Pump

作　　者：王勤湖[1] 李社坤[1] 卢文跃[1] 于海峰[1] 曹智鹏[1] 

机构地区：[1]大亚湾核电运营管理有限责任公司,广东深圳518124

出　　处：《核动力工程》2005年第S1期103-108,共6页Nuclear Power Engineering

摘　　要：论述了大亚湾和岭澳1000MW压水堆核电站反应堆冷却剂回路(一回路)主要瞬态工况对反应堆冷却剂泵的主要机械性能参数的影响,为避免主泵受瞬态干扰,以及通过改变系统参数调整来改善主泵机械参数提供了理论依据。This paper analyzed the effect of the change of operation conditions of the primary coolant system of 1000MW pressurized water reactor nuclear power plant on the main mechanic parameters of the primary coolant pump,and provided the theoretical evidences to prevent the primary coolant pump from the influence of change of operation conditions and improve the mechanical performance of the pump through the adjustment of system parameters.

关 键 词：主泵 机械性能 一回路 工况变化 

分 类 号：TL421.1[核科学技术—核技术及应用]