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Design and Verification of Reactor Power Control Based on Stepped Dynamic Matrix Controller

机译:基于阶梯动态矩阵控制器的反应堆功率控制的设计与验证

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摘要

As key equipment in nuclear power plant, the reactor power control system is adopted to strictly control and regulate the reactor power of a PWR (pressurized water reactor) in a nuclear power plant. A well-optimized predictive control algorithm based on SDMC (stepped dynamic matrix controller) is developed and introduced in this paper and applied to the power regulation of a reactor power model. In addition, the test and verification of this application is conducted by two different methods and devices: the virtual verification platform and the physical DCS (digital control system). The result of the verification suggests that the application of SDMC gains a better performance in the maximum dynamic deviation, adjustment time, overshoot, and so on.
机译:作为核电站的关键设备,采用了反应堆电力控制系统来严格控制和调节核电站PWR(加压水反应器)的反应器功率。本文开发并介绍了一种基于SDMC(阶梯式动态矩阵控制器)的优化预测控制算法,并应用于电抗电源模型的功率调节。此外,本申请的测试和验证由两种不同的方法和设备进行:虚拟验证平台和物理DCS(数字控制系统)。验证结果表明,SDMC的应用在最大动态偏差,调整时间,过冲等中的应用更好。

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  • 来源
    《Science and technology of nuclear installation》 |2019年第1期|4973120.1-4973120.11|共11页
  • 作者单位

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Sichuan Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Sichuan Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Sichuan Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Sichuan Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Sichuan Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Sichuan Peoples R China;

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