The control and data acquisition system of the DTT experiment

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-17 DOI:10.1016/j.fusengdes.2024.114777
G. Manduchi , F. Zanon , L. Boncagni , P. Mosetti , G. Martini , G. Paccagnella , C. Centioli , R. Ambrosino , F. Sartori
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Abstract

DTT, Divertor Tokamak Test facility, is currently under construction at the Frascati ENEA Research Center. Its main aim is to explore alternative solutions for the extraction of the heat generated by the fusion process. Its Control and Data Acquisition System (CODAS) will (1) orchestrate and synchronize all the DTT systems during Plasma operation and maintenance; (2) acquire data from the experiment diagnostics and plant systems and store it in an experimental database to be used for on-line and off-line analysis; (3) provide real-time Plasma control. The expected duration of the plasma discharge in DTT is in the order of some tens of seconds and therefore DTT can be considered a long-lasting experiment, involving data streaming technologies for data communication and storage. The main DTT CODAS design is based on three principles: (1) Taking inspiration from other similar experiments currently under development, namely ITER CODAC, (2) relying on proven solutions already adopted in running experiments with similar constraints and (3) taking advantage from practices widely adopted in fusion and, more in general, in industry. Despite using components already adopted in other fusion experiments, DTT CODAS is the first system that seamlessly integrates all of them.
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数字地面电视实验控制与数据采集系统
DTT,托卡马克转向器测试设施,目前正在弗拉斯卡蒂ENEA研究中心建设。其主要目的是探索提取聚变过程产生的热量的替代解决方案。其控制和数据采集系统(CODAS)将(1)在等离子运行和维护期间协调和同步所有DTT系统;(2)从实验诊断系统和植物系统获取数据,存入实验数据库,用于在线和离线分析;(3)提供实时等离子体控制。等离子体放电在DTT中的预期持续时间约为几十秒,因此DTT可以被认为是一个持久的实验,涉及数据通信和存储的数据流技术。DTT CODAS的主要设计基于三个原则:(1)从目前正在开发的其他类似实验中获得灵感,即ITER CODAC;(2)依靠在类似约束条件下运行的实验中已经采用的经过验证的解决方案;(3)利用核聚变中广泛采用的实践,更一般地说,在工业中。尽管使用了其他聚变实验中已经采用的组件,但DTT CODAS是第一个无缝集成所有组件的系统。
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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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