ITER磁体冷试验台低温恒温器设计与分析

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Qingzhou Yu , Hao Xu , Genmu Shi , Shilin Chen , Xinyuan Qian , Qingxi Yang , Thierry Schild , Guillaume Vitupier , Jose Lorenzo , Mohit Jadon , Hoyoung Kim , Xiaoming Yu , Zhaoxi Chen , Dan Zhu , Jin Chai , Rui Hu
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引用次数: 0

摘要

ITER正在建设一个磁体冷试验台(MCTB),以评估所有ITER环形场(TF)线圈和极向场1 (PF1)线圈的放电特性、淬火保护、接地绝缘和泄漏率,确保集成到ITER托卡马克时的可靠运行。MCTB低温恒温器是实验台的主要部件,设计用于兼容TF和PF1配置,为线圈提供隔热和高真空环境。本文首先概述了低温恒温器的结构,包括其外壳,多层绝缘(MLI),磁铁支撑和减压装置(PRD)。接下来,进行热分析以量化从磁铁支架到被测线圈的热传导和MLI的辐射。结果表明,当冷板的液氦管道温度上升到30 K时,通过支架对线圈的热传导负荷仍远低于400 W的极限。在辐射热方面,当MLI层数增加到50层时,TF和PF1配置线圈上的总辐射热分别约为839w和799w,均低于1000w的阈值。此外,对低温恒温器壳体在不同载荷条件下的结构响应的评估表明,其结构强度保持在10%的安全余量,即使在最恶劣的运行载荷下,屈曲载荷乘数也超过了相应的临界阈值,表明不存在塑性破坏和屈曲不稳定。针对低温恒温器壳体间大直径密封的预紧问题,提出了一种简单的密封方案,有效地抑制了密封过程中的法兰滑移。最后,回顾了低温恒温器制造的重大进展和未来的生产计划。本文可为其他磁体测试平台的设计提供有价值的技术指导。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Design and analysis of the cryostat of the ITER magnet cold test bench
ITER is constructing a Magnet Cold Test Bench (MCTB) to evaluate the discharge characteristics, quench protection, ground insulation, and leakage rates of all ITER toroidal field (TF) coils and the poloidal field 1 (PF1) coil, ensuring reliable operation when integrated into the ITER tokamak. The MCTB cryostat, the primary component of the bench, is designed for compatibility with TF and PF1 configurations, providing a thermally insulated and high-vacuum environment for the coils. This paper begins with an overview of the cryostat structure, encompassing its shells, multi-layer insulation (MLI), magnet supports, and pressure relief device (PRD). Next, thermal analyses are performed to quantify the thermal conduction from the magnet supports to the tested coil and radiation from the MLI. Results demonstrate that even when the liquid helium pipeline temperature of the cold plates rises to 30 K, the thermal conduction load on the coil via the supports remains well below the 400 W limit. Regarding radiation heat, when the number of MLI layers increases to 50, the total radiation heat on the coil for the TF and PF1 configurations is approximately 839 W and 799 W, respectively, both below the 1000 W threshold. Additionally, assessments of the cryostat shells’ structural responses under varying loading conditions reveal that a 10% safety margin in structural strength is maintained, and the buckling load multipliers exceed the corresponding critical thresholds even under the worst operational load, demonstrating the absence of plastic collapse and buckling instability. A simple sealing scheme is proposed to address the pre-tightening problem of large-diameter sealing between cryostat shells, incorporating an effective suppression solution for flange slippage during sealing. Finally, significant developments in the cryostat’s manufacturing and future production plans are reviewed. This paper can provide valuable technical guidance for the design of other magnet test platforms.
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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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