DTT ICRH天线设计优化远程处理策略的概念研究

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
G. Camera , A. Cioffi , S. Ceccuzzi , F. Marino , F.G. Lanzotti , G. Di Gironimo
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引用次数: 0

摘要

用于分流托卡马克试验(DTT)设施的离子回旋共振加热(ICRH)天线预计不仅是悬臂式的、径向移动的和完全冷却的,而且还可以远程处理:来自腔室内部的远程处理(RH)的额外挑战已经提出。远程装配和拆卸将通过超冗余机械手(HYRMAN)执行,显然需要设计远程处理部件与后面放置的组件之间的连接接口。但是,过去证明,船上射频(RF)触点的开发非常具有挑战性,引起了人们对其长期可靠性的担忧。因此,电流带的环形尺寸被减小,使它们与相对射频触点,直接通过真空容器的赤道端口。因此,只需远程处理ICRH天线正面部分的剩余几何形状,并分析和比较了备选RH策略。选择标准是基于HYRMAN载荷极限、射频性能等需要满足的要求,以及侧带屏蔽等需要保证的子部件功能。此外,选择过程还考虑了技术原因,如RH操作的数量和机器人手臂的接口,冷却回路的最小数量和弯曲风险。根据所选择的标准,选择了最令人满意的解决方案,用于设计附着在HYRMAN上的夹持器。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Conceptual study of DTT ICRH antenna designs optimizing remote handling strategy
The Ion Cyclotron Resonance Heating (ICRH) antenna for the Divertor Tokamak Test (DTT) facility is expected to be not only cantilevered, radially movable and fully cooled, but also remote handled: the additional challenge of the Remote Handling (RH) from the inner of the chamber has been posed. The remote assembly and disassembly will be performed through the HYper Redundant MANipulator (HYRMAN) and clearly require the design of the linking interfaces between the remote handled parts and the components placed behind. But the development of in-vessel Radio Frequency (RF) contacts proved in the past to be very challenging, raising concerns on their long-term reliability. Therefore, the toroidal size of the current straps has been reduced to make them, and the relative RF contacts, directly pass through the Vacuum Vessel equatorial port. Thus, only the leftover geometry of the ICRH antenna frontal part should be remote handled and alternative RH strategies have been analyzed and compared. The selecting criteria have been based on the requirements to be fulfilled like the payload limit of the HYRMAN and the RF performance, and on the subcomponents functions to be guaranteed like the side straps shielding. Furthermore, the choice process has also considered technical reasons such as the number of RH operations and interfaces to robotic arms, the minimum number of cooling circuits and the flexion risk. In compliance with the chosen criteria, the most satisfying solution has been selected to be considered for the design of the gripper to be attached to the HYRMAN.
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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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