Thermal structural analyses during cool down of the ITER toroidal field coil in the magnet cold test bench

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-07-01 Epub Date: 2025-04-11 DOI:10.1016/j.fusengdes.2025.115017
Valerio Tomarchio , Francesca Cau , José Lorenzo , María Mercedes Parody Guzmán , Damien Furfaro , Christine Hoa , Jacek Kosek , Qiu Lilong , Junjun Li , Alexandre Louzguiti , Thierry Schild , Ana Veleiro
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Abstract

A Magnet Cold Test Bench is being built in ITER to test some of the Toroidal Field Coils (TFC) and the Poloidal Field Coil PF1, before they will be assembled and installed in the tokamak. The purpose is to test the performance of the superconducting magnet in cryogenic conditions and with current.
The TF coil and its structures weigh about 300 tons and will be cooled down from 300 K to 4.5 K, with helium flow supplied by one of the three refrigeration cold boxes of the ITER cryogenic system, with a capacity of 25 kW at 4 K. The helium flows in the winding packs of the coil, through the bundle and central channel of the superconducting cables, and it also extracts heat through the numerous cooling pipes of the Casing.
From 300 K to 100 K, one major concern is the thermal stresses due to the different thermal contraction coefficients of the materials in the coil and its structure: superconducting cables composed of Nb3Sn and Copper strands, Stainless Steel for the conductor jacket, the radial plates and the casing, electrical insulation materials such as Glass Kapton Glass and epoxy resin.
The usual cool down process requirement is to control the temperature difference between helium outlet and inlet and to ensure that it does not exceed 50 K. For the Magnet Cold Test Bench (MCTB), a selected cool down scenario was simulated to comply with the thermal hydraulic criteria and to check the resulting thermal stresses are acceptable for the coil, insulation material, structure and supports.
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ITER环形场线圈在磁体冷试验台冷却过程中的热结构分析
ITER正在建造一个磁体冷试验台,用于测试一些环形场线圈(TFC)和极向场线圈PF1,然后将它们组装并安装在托卡马克中。目的是测试超导磁体在低温和电流条件下的性能。TF线圈及其结构重约300吨,将从300 K冷却到4.5 K,氦流由ITER低温系统的三个制冷冷箱之一提供,在4 K时容量为25 kW。氦气在线圈的缠绕包中流动,通过超导电缆的束和中央通道,它也通过套管的众多冷却管提取热量。从300 K到100 K,一个主要的问题是由于线圈及其结构中材料的不同热收缩系数引起的热应力:由Nb3Sn和铜股组成的超导电缆,用于导体护套的不锈钢,径向板和外壳,电气绝缘材料,如玻璃卡普顿玻璃和环氧树脂。通常的冷却过程要求是控制氦气出口和进口之间的温差,并确保其不超过50k。对于磁冷试验台(MCTB),模拟了选定的冷却场景,以符合热液压标准,并检查线圈,绝缘材料,结构和支架的热应力是否可接受。
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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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