Cristian Galperti , Federico Felici , Trang Vu , Olivier Sauter , F. Carpanese , M. Kong , G. Marceca , A. Merle , A. Pau , A. Perek , F. Pesamosca , M. Baquero-Ruiz , S. Coda , J. Decker , B. Duval , M. Gospodarczyk , A. Karpushov , S. Marchioni , A. Maier , B. Marletaz , F. Sartori
{"title":"TCV 数字实时等离子体控制系统及其应用概述","authors":"Cristian Galperti , Federico Felici , Trang Vu , Olivier Sauter , F. Carpanese , M. Kong , G. Marceca , A. Merle , A. Pau , A. Perek , F. Pesamosca , M. Baquero-Ruiz , S. Coda , J. Decker , B. Duval , M. Gospodarczyk , A. Karpushov , S. Marchioni , A. Maier , B. Marletaz , F. Sartori","doi":"10.1016/j.fusengdes.2024.114640","DOIUrl":null,"url":null,"abstract":"<div><p>Real-time plasma control systems are at the heart of operation of modern tokamaks. The control system of the TCV tokamak has recently seen a major upgrade in terms of its hardware and software components. Control algorithms are entirely programmed and tested in MATLAB/Simulink(R), executable code is automatically generated and interfaced to run-time parameters and signals through introspection using the MARTe2 software framework. The primary control system (used for coil currents, plasma current, position, shape and density control) has been upgraded by installing new analog signal inputs/output hardware, connected to two real-time computers that can operate in parallel. In addition, an EtherCAT-based real-time industrial network has been deployed to operate distributed low Input/Output count subsystems, greatly boosting the system flexibility and reach. The majority of TCV’s real-time codes have been ported to this new approach, such as the real-time equilibrium reconstruction (LIUQE), real-time Magneto-Hydro-Dynamics mode analysis algorithms, and a real-time plasma supervision, actuator management and plasma event monitor, including real-time plasma analysis using neural networks, and plasma disruption avoidance control schemes.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-09-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S0920379624004915/pdfft?md5=5fad12079caa8fcac05d400d0beab1a4&pid=1-s2.0-S0920379624004915-main.pdf","citationCount":"0","resultStr":"{\"title\":\"Overview of the TCV digital real-time plasma control system and its applications\",\"authors\":\"Cristian Galperti , Federico Felici , Trang Vu , Olivier Sauter , F. 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Overview of the TCV digital real-time plasma control system and its applications
Real-time plasma control systems are at the heart of operation of modern tokamaks. The control system of the TCV tokamak has recently seen a major upgrade in terms of its hardware and software components. Control algorithms are entirely programmed and tested in MATLAB/Simulink(R), executable code is automatically generated and interfaced to run-time parameters and signals through introspection using the MARTe2 software framework. The primary control system (used for coil currents, plasma current, position, shape and density control) has been upgraded by installing new analog signal inputs/output hardware, connected to two real-time computers that can operate in parallel. In addition, an EtherCAT-based real-time industrial network has been deployed to operate distributed low Input/Output count subsystems, greatly boosting the system flexibility and reach. The majority of TCV’s real-time codes have been ported to this new approach, such as the real-time equilibrium reconstruction (LIUQE), real-time Magneto-Hydro-Dynamics mode analysis algorithms, and a real-time plasma supervision, actuator management and plasma event monitor, including real-time plasma analysis using neural networks, and plasma disruption avoidance control schemes.
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.