Enabling model-based scenario control in EAST by fast surrogate modeling within COTSIM

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Z. Wang , E. Schuster , T. Rafiq , Y. Huang , Z. Luo , Q. Yuan , J. Barr
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引用次数: 0

Abstract

The Control-Oriented Transport Simulator (COTSIM) is a fast, modular code designed to predict the evolution of both equilibrium and internal profiles in the EAST tokamak. Built on MATLAB/Simulink®, COTSIM is tailored for iterative control design, making it suitable for applications such as pulse design, feedforward scenario optimization, feedback-control testing prior to implementation, and real-time estimation and optimization. Recent advancements have enhanced its prediction accuracy for EAST while maintaining computational efficiency through the integration of neural-network-based surrogate models for the Multi-Mode Anomalous Transport Module (MMM), GENRAY/CQL3D (Lower Hybrid Wave [LHW]), and NUBEAM (Neutral Beam Injection [NBI]). Additionally, the transport solver has been coupled with both fixed-boundary and free-boundary equilibrium solvers. This study demonstrates the development and testing of model-based optimal feedback controllers in COTSIM simulations. These controllers regulate key plasma properties crucial for advanced tokamak scenarios, including the safety factor (q) at various spatial locations, plasma internal energy (W), normalized beta (βN), and internal inductance (li). Control actuators include plasma current, plasma density, low-frequency (2.45 GHz) and high-frequency (4.60 GHz) LHW powers, and individual NBI powers. To validate these control algorithms, experimental testing has been conducted on EAST. Results from simulations and experiments demonstrate the ability to regulate scenario-defining plasma properties, suggesting COTSIM’s utility as a tool for advanced tokamak control development.
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来源期刊
Fusion Engineering and Design
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.
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