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常压下RRA系统性能试验分析

Experimental Analysis of RRA System Performance at Atmospheric Pressure
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摘要 余热排出系统(RRA)能将反应堆冷却剂温度维持在冷停堆工况,并可满足换料和维修操作所需要的时间。在维修冷停堆工况下(堆芯有燃料),保证任何一台蒸汽发生器维修时,维持冷却剂温度低于60℃,使维修人员能够进入蒸汽发生器人孔,同时还要保证堆芯的冷却。本试验需要验证在此工况下,在主管道环路高液位报警出现时,反应堆冷却剂不会进入蒸汽发生器底封头而造成工作人员额外的放射性污染。在主环路低液位报警时,余热排出泵在单泵设计要求的最大流量下运行时,不会发生汽蚀。当维修冷停堆工况下投用三环路热段主管道环路液位计RCP300MN时,液位的升降应足够缓慢,以避免液位变化过快而引起的仪表显示故障。 Residual Heat Removal System(RRA) can be used to maintain the reactor coolant temperature at cold shutdown conditions to offer the time required for the refueling and maintenance operations. In the maintenance in the cold shutdown condition(with the fuel in the reactor), this system will keep the reactor coolant temperature less than 60 centigrade for the repairman to get into the manhole of any one of the steam generators and maintain the reactor cooling. In this test, it requires to prove that in this condition the reactor coolant does not enter the steam generator bottom head to result in additional staff radioactive contamination when the primary loop high level alarm occurs. The residual heat removal pump is required to run without cavitation even at its designed maximum flow rate when the primary loop low level alarm occurs. The level of the primary loop should change slowly to avoid the instrument false when the RCP300 MN is put into use during the maintenance cold shutdown condition.
作者 许兆平
出处 《核动力工程》 EI CAS CSCD 北大核心 2015年第S1期118-121,共4页 Nuclear Power Engineering
关键词 余热排出泵 蒸汽发生器 维修冷停堆 汽蚀 Residual heat removal pump,Steam generator,Cold shutdown for maintenance,Cavitation
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