Domenico Frattolillo , Luigi Emanuel di Grazia , Massimiliano Mattei , Federico Pesamosca
{"title":"Magnetic control strategies to reduce first wall heat loads in ITER","authors":"Domenico Frattolillo , Luigi Emanuel di Grazia , Massimiliano Mattei , Federico Pesamosca","doi":"10.1016/j.fusengdes.2025.115203","DOIUrl":null,"url":null,"abstract":"<div><div>First wall heat load control is one of the functionalities that will be implemented in the ITER Plasma Control System to maintain plasma heat fluxes and the consequent first wall (FW) temperatures within tolerable limits during a plasma discharge. As part of this strategy, the magnetic controller for the plasma shape will act as an inner loop for first wall heat load control, guaranteeing a first line of defense. In this work we propose to use a FW temperature controller (FWTC) designed as a virtual actuator, modifying the reference plasma equilibrium in order to limit the excess of FW temperature in real-time. A fixed number of plasma equilibrium variations, or FWTC patterns, is first optimized to achieve a plasma heat flux reduction over several FW regions at a reasonable poloidal field coil current control cost, including the second x-point area. Subsequently, an on/off multi-input–multi-output FW temperature control with hysteresis is designed to request a linear combination of FWTC patterns to the magnetic controller. The control scheme implements an integral action with limited authority on gap and active coil current requests, including a hysteresis logic to avoid chattering. The control problem is particularly challenging because of the nonlinear relationship between plasma position and FW heat fluxes featuring magnetic shadowing of neighboring first wall panels. The flexibility of the presented algorithm is illustrated in control-oriented simulations, covering both the ITER Start of Research Operations (controlling the predicted temperature of the inertially cooled FW) and the planned Deuterium-Tritium campaign (controlling the instantaneous temperature of the actively cooled FW).</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115203"},"PeriodicalIF":1.9000,"publicationDate":"2025-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625003990","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
First wall heat load control is one of the functionalities that will be implemented in the ITER Plasma Control System to maintain plasma heat fluxes and the consequent first wall (FW) temperatures within tolerable limits during a plasma discharge. As part of this strategy, the magnetic controller for the plasma shape will act as an inner loop for first wall heat load control, guaranteeing a first line of defense. In this work we propose to use a FW temperature controller (FWTC) designed as a virtual actuator, modifying the reference plasma equilibrium in order to limit the excess of FW temperature in real-time. A fixed number of plasma equilibrium variations, or FWTC patterns, is first optimized to achieve a plasma heat flux reduction over several FW regions at a reasonable poloidal field coil current control cost, including the second x-point area. Subsequently, an on/off multi-input–multi-output FW temperature control with hysteresis is designed to request a linear combination of FWTC patterns to the magnetic controller. The control scheme implements an integral action with limited authority on gap and active coil current requests, including a hysteresis logic to avoid chattering. The control problem is particularly challenging because of the nonlinear relationship between plasma position and FW heat fluxes featuring magnetic shadowing of neighboring first wall panels. The flexibility of the presented algorithm is illustrated in control-oriented simulations, covering both the ITER Start of Research Operations (controlling the predicted temperature of the inertially cooled FW) and the planned Deuterium-Tritium campaign (controlling the instantaneous temperature of the actively cooled FW).
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.