H-Mode density limit disruption avoidance in ASDEX Upgrade, TCV and JET

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
B. Sieglin , M. Maraschek , A. Gude , F. Klossek , F. Felici , M. Bernert , O. Kudlacek , A. Pau , L. Piron , M. Lennholm , K. Kirov , S. Hongjuan , A. Parrott , P. Fox , O. Sauter , C. Stuart , C. Ashe , A. Huber , W. Treutterer , ASDEX Upgrade Team , TCV Team , JET contributors , EUROfusion WPTE Team
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引用次数: 0

Abstract

In recent years a strong effort has been made to investigate disruption avoidance schemes in order to aid the development of integrated operational scenarios for ITER. Within the EUROfusion programme the disruptive H-Mode density limit (HDL) has been studied on ASDEX Upgrade, TCV and JET. This paper presents the results from these studies in the view of the plasma control system (PCS).
The successful migration of disruption avoidance schemes based on direct measurements as well as state space based HDL observers across the devices has been demonstrated. HDL disruption avoidance using continuous control is now routinely available at TCV and ASDEX Upgrade, using both observer types. Exception handling based disruption avoidance has been utilized on all three devices. All three control systems allowed the implementation of the desired schemes with minimal adaptions, implementing the equivalent detection algorithms. Using the same experimental methodology it is confirmed that the XPR/MARFE movement, which is preceding the disruptive HDL, is similar on all three devices. The main difference lies in the associated times scales which increase with machine size. This would be beneficial for large devices, such as ITER and DEMO, since it would give the control system more time to apply the appropriate disruption avoidance action. As actuator auxiliary heating, gas flow and plasma shaping have been successfully demonstrated.
This work gives input for the requirements of future tokamak control systems which should enable the necessary disruption avoidance schemes. All disruption avoidance schemes developed during the studies can be implemented in the ITER PCS with its currently foreseen capabilities.
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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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