期刊文献+

模糊逻辑控制在核动力系统中的应用和问题探讨 被引量:3

Review on Applications of Fuzzy Logic Control in Nuclear Power Systems and Issue Discussions
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摘要 模糊逻辑控制(FLC)在核动力系统中的应用研究表明,FLC对核动力系统的智能化和全自动化控制而言,是一种有效而可行的先进控制方法。本文对此方面的研究成果进行了全面回顾和总结,并探讨了FLC应用研究和实践中需要重点解决的问题。 The studies on applications of fuzzy logic control (FLC) in nuclear power systems demonstrate that FLC is an effective and feasible advanced method for intelligent and full-automatic control of nuclear power systems. A complete review and summary of the achievements from FLC application research are presented, and some key issues to be solved in the application research and practical use of FLC are discussed.
出处 《核动力工程》 EI CAS CSCD 北大核心 2004年第2期160-163,共4页 Nuclear Power Engineering
基金 国家自然科学基金资助项(60174015)
关键词 模糊逻辑控制 核动力系统 智能化 全自动化 Automation Intelligent control Nuclear energy Nuclear reactors Programmable logic controllers
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参考文献31

  • 1朱雪耀,赵福宇,万百五.压水堆负荷跟踪的模糊控制系统[J].核动力工程,1998,19(5):456-461. 被引量:12
  • 2吕志松,崔震华.稳压器模糊控制系统初步研究[J].核动力工程,2001,22(1):83-86. 被引量:14
  • 3滕树杰,张乃尧,崔震华.核动力装置蒸汽发生器水位的分层模糊自适应控制[J].控制与决策,2002,17(6):933-936. 被引量:19
  • 4Bubak M,Moscinski J,Jewulski J.Fuzzy-Logic Approachto HTR Nuclear Power Plant Model Control[J].Ann Nucl Energy,1983,10(9):467-471. 被引量:1
  • 5Kinoshita M,Fukuzaki T,Stoh T,etc.An Automatic Operation Method for Control Rods in BWR Plants[C].See:In-Core Instrumentation and Reactor Core Assessment,Proceedings of Specialists' Meeting,Cadarache,France:1988,213~220. 被引量:1
  • 6Terunuma S,Kishiwada K,Takahashi H,etc.Application of Fuzzy Algorithm for the Feedwater Control System in Fugen HWR[C].See:Proceedings of an International Conference on Man-Machine Interface in the Nuclear Industry:1988,463~473. 被引量:1
  • 7Bernard J A.Use of a Rule-Based System for Process Control[J].IEEE Control System Magazine,1988,8(5):3-13. 被引量:1
  • 8Pramath Ramaswamy,Robert Edwards,Kwang Y Lee.An Automatic Tuning Method of Fuzzy Logic Controller for Nuclear Reactors[J].IEEE Trans Nucl Sci,1993,40:1253-1262. 被引量:1
  • 9Heger A S,Alang-Rashid N K,Jamshidi M.Application of Fuzzy Logic in Nuclear Reactor Control Part I:An Assessment of State-of-the-Art[J].Nucl Safety,1995,36(1):109-121. 被引量:1
  • 10Lin X Z,Ruan D.Comparative Study of Fuzzy Control,PID Control,and Advanced Fuzzy Control for Simulating a Nuclear Reactor Operation[J].International Journal of General Systems,2000,29(2):263-279. 被引量:1

二级参考文献8

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  • 1王书斌,单胜男,罗雄麟.基于T-S模糊模型与粒子群优化的非线性预测控制[J].化工学报,2012,63(S1):176-187. 被引量:8
  • 2Mehrdad N, Mohammad B, Amir A. A neural network controller for load following operation of nuclear reactors[J]. Annals of Nuclear Energy, 2002, 29(6): 751-760. 被引量:1
  • 3Arab-Alibeik H, Setayeshi S. Adaptive control ofa PWR core power using neural networks[J]. Annals of Nuclear Energy, 2005, 32(6): 588-605. 被引量:1
  • 4Saif M. A novel approach for optimal control of a pressurized water reactor[J]. IEEE Transactions on Nuclear Science, 1989, 36(1): 1317-1325. 被引量:1
  • 5Saif M. Suboptimal projective control of a pressurized water reactor [J]. IEEE Transactions on Nuclear Science, 1989, 36(6): 2459-2465. 被引量:1
  • 6Ben-Abdennour A, Edwards R M, Lee K Y. LQG/LTR robust control of nuclear reactors with improved temperature performance[J]. IEEE Transactions on Nuclear Science, 1992, 39(6): 2286-2294. 被引量:1
  • 7Dong Zhe, Feng Junting, Huang Xiaojin. Nonlinear observer-based feedback dissipation load-following control for nuclear reactors [J]. IEEE Transactions on Nuclear Science, 2009, 56(1): 272-285. 被引量:1
  • 8Xiong Li, Liu Dichen, Wang Bo, et al. Dynamic characteristics analyse of pressurized water reactor nuclear power plant based on PSASP[C]//4th IEEE Conference on Industrial Electronics and Applications. Xi'an, China: IEEE, 2009: 3629-3634. 被引量:1
  • 9Li Xiong, Liu Dichen, Shi Xi, et al. Research and analyse for pressurized water reactor plant into power system dynamics simulation[C]//Asia-Pacific Power and Energy Engineering Conference. Wuhan, China: IEEE, 2009: 1-5. 被引量:1
  • 10Zhao Jie, Wu Ping, Liu Dichen. User-defined modeling of pressurized water reactor nuclear power plant based on PSASP and analysis of its characteristics[C]//Asia-Pacific Power and Energy Engineering Conference. Wuhan, China: IEEE, 2009: 146. 被引量:1

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