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Dynamic Matrix Control for the Thermal Power of MHTGR-Based Nuclear Steam Supply System

Author

Listed:
  • Di Jiang

    (Institute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China)

  • Zhe Dong

    (Institute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China)

  • Miao Liu

    (Institute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China)

  • Xiaojin Huang

    (Institute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, China)

Abstract

The modular high temperature gas-cooled reactor (MHTGR) based nuclear steam supplying system (NSSS) is constituted by an MHTGR, a once-through steam generator (OTSG) and can generate superheated steam for industrial heat or electric power generation. The wide range closed-loop stability is achieved by the recently proposed coordinated control law, in which the neutron flux and the temperatures of both main steam and primary coolant are chosen as controlled variables, and the flowrates of both primary and secondary loop and the control rod speed are chosen as manipulated variables. However, the thermal power is only controlled in open loop manner and hence could be further optimized through feedback. Motivated by this, a dynamic matrix control (DMC) is proposed for optimizing the thermal power of MHTGR based NSSS. A simple step-response model with the thermal power response data is utilized in designing the DMC. The design objective of DMC is to optimize the deviation of the thermal power from its reference under its rate constraint. Then, by the virtue of strong stability of existing control law and optimization ability of DMC, a cascade control structure is implemented for the thermal power optimization, with the coordinated control law in the inner loop and DMC in the outer loop. Numerical simulation results show the satisfactory improvement of thermal power response. This cascade control structure inherits the advantages of both proportional-integral-differential (PID) control and DMC, by which the zeros offset and the short settling time of thermal power are realized.

Suggested Citation

  • Di Jiang & Zhe Dong & Miao Liu & Xiaojin Huang, 2018. "Dynamic Matrix Control for the Thermal Power of MHTGR-Based Nuclear Steam Supply System," Energies, MDPI, vol. 11(10), pages 1-15, October.
    • Handle: RePEc:gam:jeners:v:11:y:2018:i:10:p:2651-:d:173716
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    References listed on IDEAS

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    1. Siwei Han & Li Sun & Jiong Shen & Lei Pan & Kwang Y. Lee, 2018. "Optimal Load-Tracking Operation of Grid-Connected Solid Oxide Fuel Cells through Set Point Scheduling and Combined L1-MPC Control," Energies, MDPI, vol. 11(4), pages 1-23, March.
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    4. Dong, Zhe & Zhang, Zuoyi & Dong, Yujie & Huang, Xiaojin, 2018. "Multi-layer perception based model predictive control for the thermal power of nuclear superheated-steam supply systems," Energy, Elsevier, vol. 151(C), pages 116-125.
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    Cited by:

    1. Zhe Dong & Zhonghua Cheng & Yunlong Zhu & Xiaojin Huang & Yujie Dong & Zuoyi Zhang, 2023. "Review on the Recent Progress in Nuclear Plant Dynamical Modeling and Control," Energies, MDPI, vol. 16(3), pages 1-19, February.
    2. Jiang, Di & Dong, Zhe, 2019. "Practical dynamic matrix control of MHTGR-based nuclear steam supply systems," Energy, Elsevier, vol. 185(C), pages 695-707.
    3. Jiang, Di & Dong, Zhe, 2020. "Dynamic matrix control for thermal power of multi-modular high temperature gas-cooled reactor plants," Energy, Elsevier, vol. 198(C).
    4. Kai Xiao & Yiliang Li & Pengcheng Yang & Ying Zhang & Yang Zhao & Xiaofei Pu, 2022. "Study on IMC-PID Control of Once-Through Steam Generator for Small Fast Reactor," Energies, MDPI, vol. 15(20), pages 1-20, October.

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