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Volume 45 Issue S2
Jan.  2025
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Du Ming, Bian Shujie, Niu Yuguang, Yuan Jinxiao, Chen Rigang. Research on Automatic Control of SGTR Post-accident Safety Injection Process Based on Intelligent Algorithm[J]. Nuclear Power Engineering, 2024, 45(S2): 189-196. doi: 10.13832/j.jnpe.2024.S2.0189
Citation: Du Ming, Bian Shujie, Niu Yuguang, Yuan Jinxiao, Chen Rigang. Research on Automatic Control of SGTR Post-accident Safety Injection Process Based on Intelligent Algorithm[J]. Nuclear Power Engineering, 2024, 45(S2): 189-196. doi: 10.13832/j.jnpe.2024.S2.0189

Research on Automatic Control of SGTR Post-accident Safety Injection Process Based on Intelligent Algorithm

doi: 10.13832/j.jnpe.2024.S2.0189
  • Received Date: 2024-06-15
  • Rev Recd Date: 2024-09-06
  • Publish Date: 2025-01-06
  • Following a steam generator tube rupture (SGTR) accident at a nuclear power plant, the manual adjustment control method is commonly employed, and the adjustment of the safety injection process is one of the difficulties faced by operators. For this process, the main adjustment mechanism and characteristics of the object are analyzed firstly in this paper. Combined with the experience of the operator, the automatic control structure of the safety injection control process is summarized, and the corresponding parameter setting method is designed. The intelligent elements such as adaptive PID, intelligent feedforward and reinforcement learning are integrated, so that the intelligent control strategy of the safety injection control process is innovatively proposed. In order to complete the strategy validation on the M310 full-range simulator developed by a company, this paper first develops the intelligent computing engine, then completed the control strategy configuration on the intelligent computing engine, then completes the control strategy configuration on the intelligent computing engine, and completes the real-time communication of the control signals through the MySQL. Through the simulation and test verification of different breach accidents in the simulator, the intelligent control strategies proposed in this paper are all able to realize the automatic adjustment of the injection control process, the actual cooling rate deviation is 5.89% of the cooling rate set value, the matching effect of the subcooling degree and the regulator level adjustment is good, and the performance is higher than the average of the manipulator's manual execution of the task.

     

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  • [1]
    郑文波. 核电厂运行安全常见问题及防控措施的探讨[J]. 科技资讯,2021, 19(26): 27-29.
    [2]
    王丰景. 核电厂蒸汽发生器传热管破裂事故处理研究[J]. 中小企业管理与科技,2020(12): 156-157.
    [3]
    胡伟晨,刘建全,赵鹏程,等. 基于RELAP5的蒸汽发生器传热管断裂事故分析[J]. 核科学与工程,2022, 42(2): 398-407. doi: 10.3969/j.issn.0258-0918.2022.02.022
    [4]
    林萌,苏云,胡锐,等. 核电站工程模拟器用于SGTR事故仿真分析研究[J]. 原子能科学技术,2005, 39(3): 240-245. doi: 10.3969/j.issn.1000-6931.2005.03.012
    [5]
    石俊英. WWER-1000型核电站SGTR事故分析[J]. 核动力工程,2002, 23(2): 51-55. doi: 10.3969/j.issn.0258-0926.2002.02.011
    [6]
    张仕玉. 核电厂蒸汽发生器传热管破裂事故处理策略分析[J]. 河南科技,2019(7): 49-50. doi: 10.3969/j.issn.1003-5168.2019.07.022
    [7]
    段智勇,刘永阔,夏虹,等. 核电站故障诊断与故障程度评估方法[J]. 应用科技,2016, 43(4): 1-5.
    [8]
    GURSEL E, REDDY B, KHOJANDI A, et al. Using artificial intelligence to detect human errors in nuclear power plants: A case in operation and maintenance[J]. Nuclear Engineering and Technology, 2023, 55(2): 603-622. doi: 10.1016/j.net.2022.10.032
    [9]
    沈学泽,张力,青涛,等. 核电厂事故规程信息化系统对操纵员工作负荷的影响研究[J]. 工业工程,2022, 25(6): 146-151,159. doi: 10.3969/j.issn.1007-7375.2022.06.017
    [10]
    STOJANOVIC L, DINIC M, STOJANOVIC N, et al. Big-data-driven anomaly detection in industry (4.0): An approach and a case study[C]//2016 IEEE International Conference on Big Data (Big Data). Washington, DC, USA: IEEE, 2016.
    [11]
    ZHAO K. An integrated approach to performance monitoring and fault diagnosis of nuclear power systems[D]. Knoxville: University of Tennessee, 2005.
    [12]
    MA J P, JIANG J. Applications of fault detection and diagnosis methods in nuclear power plants: A review[J]. Progress in Nuclear Energy, 2011, 53(3): 255-266. doi: 10.1016/j.pnucene.2010.12.001
    [13]
    LIU F, ZHANG Z J, PENG M J. Research on the computerized symptom-oriented procedures of nuclear power plants[C]//16th International Conference on Nuclear Engineering. Orlando: ASME, 2008.
    [14]
    刘立欣,王喆. 核电厂SGTR规程优化研究[J]. 核动力工程,2022, 43(4): 126-130. doi: 10.13832/j.jnpe.2022.04.0126.
    [15]
    刘海宇,李力,李骜. 基于任务分析的核电厂计算机化运行规程人机界面研究[J]. 核科学与工程,2021, 41(3): 649-656. doi: 10.3969/j.issn.0258-0918.2021.03.029
    [16]
    LIU L X. Research on impact of pressurizer heater block on SGTR overfill analysis[C]//2017 25th International Conference on Nuclear Engineering. Shanghai: American Society of Mechanical Engineers, 2017.
    [17]
    LEE S, KIM J. Design of computerized operator support system for technical specification monitoring[J]. Annals of Nuclear Energy, 2022, 165: 108661. doi: 10.1016/j.anucene.2021.108661
    [18]
    KIM H, ARIGI A M, KIM J. Development of a diagnostic algorithm for abnormal situations using long short-term memory and variational autoencoder[J]. Annals of Nuclear Energy, 2021, 153: 108077. doi: 10.1016/j.anucene.2020.108077
    [19]
    HSIEH M H, HWANG S L, LIU K H, et al. A decision support system for identifying abnormal operating procedures in a nuclear power plant[J]. Nuclear Engineering and Design, 2012, 249: 413-418. doi: 10.1016/j.nucengdes.2012.04.009
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