Cascade Internal Model Control scheme for PID feedback control on Keda Torus eXperiment

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2024-07-15 DOI:10.1016/j.fusengdes.2024.114592

Zhen Tao , Adil Yolbarsop , Yuan Zhang , Wentan Yan , Zheng Chen , Xianhao Rao , Shunrong Ren , Furen Tian , Xiuming Wang , Wenzhe Mao , Zian Wei , Zixi Liu , Chu Zhou , Adi Liu , Tao Lan , Jinlin Xie , Haiyang Zhou , Xiaohui Wen , Hai Wang , Ge Zhuang , Wandong Liu

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引用次数: 0

Abstract

KTX, a reversed field pinch (RFP) device, is equipped with a robust Magnetohydrodynamic (MHD) magnetic field feedback control system, which comprises two distinct loops: an inner loop used for current control to generate a magnetic field, and an outer loop dedicated to magnetic field control; these loops operate in a cascading manner. The Proportional–Integral–Derivative (PID) control methodology is employed. In the pursuit of achieving superior performance, mathematical analysis is conducted on both control loops. This rigorous examination culminates in the design of an Internal Model Control (IMC) PID controller. Simulations are employed and further verified through experimental investigations. A magnetic field with fast and accurate response time has been successfully achieved.

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用于 Keda Torus 试验 PID 反馈控制的级联内部模型控制方案

KTX 是一种反向磁场夹持（RFP）装置，配备了强大的磁流体动力（MHD）磁场反馈控制系统，该系统由两个不同的环路组成：一个内环用于控制电流以产生磁场，另一个外环专门用于磁场控制；这些环路以级联方式运行。系统采用比例-积分-微分（PID）控制方法。为了实现卓越的性能，对两个控制回路都进行了数学分析。通过严格的检查，最终设计出内部模型控制 (IMC) PID 控制器。仿真结果通过实验研究得到进一步验证。成功实现了快速、准确响应的磁场。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.