张红岩, 师二兵, 方成跃. 二回路非能动余热排出系统设计要素分析[J]. 中国舰船研究, 2017, 12(3): 98-104. DOI: 10.3969/j.issn.1673-3185.2017.03.014
引用本文: 张红岩, 师二兵, 方成跃. 二回路非能动余热排出系统设计要素分析[J]. 中国舰船研究, 2017, 12(3): 98-104. DOI: 10.3969/j.issn.1673-3185.2017.03.014
ZHANG Hongyan, SHI Erbing, FANG Chengyue. Design factors analyses of second-loop PRHRS[J]. Chinese Journal of Ship Research, 2017, 12(3): 98-104. DOI: 10.3969/j.issn.1673-3185.2017.03.014
Citation: ZHANG Hongyan, SHI Erbing, FANG Chengyue. Design factors analyses of second-loop PRHRS[J]. Chinese Journal of Ship Research, 2017, 12(3): 98-104. DOI: 10.3969/j.issn.1673-3185.2017.03.014

二回路非能动余热排出系统设计要素分析

Design factors analyses of second-loop PRHRS

  • 摘要:
      目的  为研究二回路非能动余热排出系统(PRHRS)的运行特性,
      方法  借助瞬态热工安全分析程序RELAP5,建立主冷却剂系统和二回路非能动余热排出系统的仿真模型。对二回路非能动余热排出系统的3个关键设计要素(设计负荷、应急补水箱及蒸汽侧隔离阀开启速度)开展全部电源丧失事故及单侧主给水管道断裂事故工况下的瞬态计算和对比分析,
      结果  分析结果表明:设计负荷需综合考虑系统安全性与冷却速率;应急补水箱向蒸汽发生器注水有利于事故后的初期冷却,而降低隔离阀开启速度可改善系统的启动特性。
      结论  计算分析结果可为核动力装置二回路非能动余热排出系统设计提供参考。

     

    Abstract: In order to study the operating characteristics of a second-loop Passive Residual Heat Removal System (PRHRS), the transient thermal analysis code RELAP5 is used to build simulation models of the main coolant system and second-loop PRHRS. Transient calculations and comparative analyses under station blackout accident and one-side feed water line break accident conditions are conducted for three critical design factors of the second-loop PRHRS:design capacity, emergency makeup tank and isolation valve opening speed. The impacts of the discussed design factors on the operating characteristics of the second-loop PRHRS are summarized based on calculations and analyses. The analysis results indicate that the system safety and cooling rate should be taken into consideration in designing PRHRS's capacity, and water injection from emergency makeup tank to steam generator can provide advantage to system cooling in the event of accident, and system startup performance can be improved by reducing the opening speed of isolation valve. The results can provide references for the design of the second-loop PRHRS in nuclear power plants.

     

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