NST  >> Vol. 5 No. 3 (July 2017)

    核电站凝水系统的状态预测方法研究
    A Study of Condition Forecasting Method of Condensate Water System in Nuclear Power Plant

  • 全文下载: PDF(957KB) HTML   XML   PP.153-163   DOI: 10.12677/NST.2017.53020  
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作者:  

张欣:黑龙江省电力科学研究院,黑龙江 哈尔滨

关键词:
凝水系统状态预测仿真模型Condensate Water System Condition Forecasting Simulation Mode

摘要:

运行支持系统可以辅助操纵员进行决策分析,对于提高核电站的安全性和可靠性具有重要意义。而发生故障后的状态预测方法是目前运行支持技术中的热点问题,本文提出基于机理仿真的凝水系统状态预测方法。在进行故障特性分析的基础上,将从仪控系统中采集到的实际测量数据引入机理仿真过程中,在核电站正常运行时仿真模型能与之同步运行;当电站发生故障后,能快速完成异常的识别并切换至超实时运行进行运行状态预测。通过采集600 MW全范围仿真机中的正常和故障数据进行实验测试表明,本方法可以实现有效的状态预测,可以辅助操纵员评估故障的发展变化趋势和严重程度。

Operation support system can improve the safety, reliability and economy of nuclear power plant, condition forecasting technology is one of the hot research problems in operation support system. The major work of this thesis is researching the technology of condition forecasting of condensate water system. By a detailed analysis of the composition and the failure characteristics of the condensate water system, the paper uses the simulation model to predict the condition of the equipment. When the equipment is in normal, the system can simulate the current state in realtime; when the failure occurs, the condition forecasting module based on simulation model run in ultrareal time to predict the future states and anomalies of the equipment. The method has been proven by simulation validation. Results show that the condition forecasting system meets the requirements of predicting the state of nuclear power plants, and provides sufficient information for the operators.

文章引用:
张欣. 核电站凝水系统的状态预测方法研究[J]. 核科学与技术, 2017, 5(3): 153-163. https://doi.org/10.12677/NST.2017.53020

参考文献

[1] 谢春丽. GM (1, 1)灰色模型在核电设备趋势预测中的应用[J]. 核科学与工程,2007, 27(2): 138-142.
[2] 刘文学, 彭敏俊. 核电站反应堆冷却剂系统在线仿真研究[D]: [硕士学位论文]. 哈尔滨: 哈尔滨工程大学, 2008.
[3] Wang, Y.Q., Li, F., et al. (2003) On-Line Monitoring the Incore Power Distribution by Using Excore Ion-Chambers. Nuclear Engineering and Design, 22, 15-326.
https://doi.org/10.1016/s0029-5493(03)00183-3
[4] 罗征培, 李富, 王亚奇, 等. 在核反应堆安全运行中使用在线监视技术的设想[J]. 核科学与工程, 2000, 20(1): 32- 38.
[5] Westinghouse Electric Company (1998) BEACON Core Monitoring System General Technical Description.
[6] Wakabayashi, J. 日本核电站支持系统的开发[J]. 国外核动力, 1999, 5(4): 1-12.
[7] Chou, F.-H. and Ho, C.-S. (2000)Online Transient Behavior Prediction in Nuclear Power Plant. Applied Artificial Intelli-gence, 10, 975-1001.
https://doi.org/10.1080/08839510050179464
[8] Jia, X., Tso, C.P., Jolly, P., et al. (1999) Distributed Steady and Dynamic Modeling of Dry-Expansion Evaporators. International Journal of Refrigeration, 22, 126-136.
https://doi.org/10.1016/S0140-7007(98)00043-7
[9] Mithraratne, P., Wijeysundera, N.E. and Bong, T.Y. (2000) Dynamic Simulation of a Thermostatically Controlled Counter-Flow Evaporator. International Journal of Refrigeration, 23, 174-189.
https://doi.org/10.1016/S0140-7007(99)00048-1
[10] Wang, G.S. (2009) The Numerical Simulation of Power Plant Condenser Thermodynamic Performance. China Electric Power Press, Beijing.
[11] Zhang, Z.D. (1993) Condensers of Large Power Station. China Machine Press, Beijing.