中国安全科学学报 ›› 2018, Vol. 28 ›› Issue (3): 138-143.doi: 10.16265/j.cnki.issn1003-3033.2018.03.024

• 安全工程技术科学 • 上一篇    下一篇

系列间切换中多因素对核电厂RRI系统压力的影响

高畅1,2 工程师, 苑景凯3 高级工程师, 张坤1,2 工程师, 王永1,2 高级工程师, 邹金强1,2 高级工程师   

  1. 1 中核武汉核电运行技术股份有限公司, 湖北 武汉 430223;
    2 核动力运行研究所, 湖北 武汉 430074;
    3 中核核电运行管理有限公司, 浙江 海盐 314300
  • 收稿日期:2018-01-10 修回日期:2018-02-26 出版日期:2018-03-28 发布日期:2020-11-09
  • 作者简介:高 畅 (1988—),男,河南信阳人,硕士,工程师,主要从事核电系统及设备的热工水力研究。E-mail:gcma19@163.com。

Influences of multiple factors on pressure of RRI system in nuclear power plant

GAO Chang1,2, YUAN Jingkai3, ZHANG Kun1,2, WANG Yong1,2, ZOU Jinqiang1,2   

  1. 1 China Nuclear Power Operation Technology Corporation Ltd., Wuhan Hubei 430223, China;
    2 Research Institute of Nuclear Power Operation, Wuhan Hubei 430074, China;
    3 China Nuclear Power Operation Management Corporation.Ltd, Haiyan Zhejiang 314300, China
  • Received:2018-01-10 Revised:2018-02-26 Online:2018-03-28 Published:2020-11-09

摘要: 为解决核电厂设备冷却水系统(RRI系统)系列间切换过程出现的安全阀频繁起跳问题,以某核电厂为研究对象,运用Flowmaster软件计算该核电厂RRI系统系列间切换过程的压力变化,研究关阀时间、泵旁通流量、控制阀与泵的开启时间间隔等因素对于系统压力变化的影响,并验证仿真结论。研究结果表明:增加设备冷却水泵的旁通流量、在设备冷却水泵达到额定转速前开启控制阀均能有效减缓启泵瞬间的压力波动;随着EAS热交换器冷侧管线控制阀关阀时间的增加会减弱关阀瞬间产生的水锤现象,减缓系统压力波动。

关键词: 核电厂, 设备冷却水系统(RRI系统), 压力波动, 特征线法, 瞬态计算

Abstract: In order to solve the problem of frequent opening of safety valve when switching between different series of RRI system in nuclear power plant, a certain nuclear power plant in China was taken as research object, and the Flowmaster software was used to simulate the pressure fluctuation in the process of switching between different series of cooling water system. Relations between pressure and influent factors, such as closing valve time, bypass flow rate of the pump, the opening time interval between the control valve and the pump, were studied. The results of simulation are verified. The results show that increasing the bypass flow of cooling water pump or opening the control valves before the equipment cooling water pump reaching the rated speed, can effectively reduce the pressure fluctuation when startup the pump, that increasing the closing time of control valves on the cold side of EAS heat exchanger can restrain the water hammer phenomenon during the instance of valve closing, and that the related commissioning results verify the conclusion of the simulation.

Key words: nuclear power plant, equipment cooling water system(RRI), pressure fluctuation, method of characteristics, transient calculation

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