From Design to Development Phase of the ITER Correction Coils
From Design to Development Phase of the ITER Correction Coils
复制标题
DOI：
10.1109/tasc.2010.2089954
复制
发表时间：
2011-06
影响因子：
1.8
通讯作者：
A. Foussat;N. Dolgetta;C. Jong;P. Libeyre;N. Mitchell;Weiyue Wu;Liping Liu;S. Du;Xufeng Liu-Xufeng
中科院分区：
文献类型：
--
作者：
A. Foussat;N. Dolgetta;C. Jong;P. Libeyre;N. Mitchell;Weiyue Wu;Liping Liu;S. Du;Xufeng Liu-Xufeng
ITER 内的校正线圈系统 (CC) 旨在减少因用于限制、加热和塑造等离子体的其他线圈的组装或几何缺陷而产生的磁误差场范围。拟议的磁体系统由三组各 6 个线圈组成，分别位于托卡马克装置的顶部 (TCC)、侧面 (SCC) 和底部 (BCC)，并使用工作温度为 4.2 K 的 NbTi 电缆套管超导导体 (CICC)。ITER 组织 (IO) 和中国科学院等离子体物理研究所 (ASIPP) 正在共同准备技术规范的定义和即将推出的校正资格计划线圈。所提出的设计包括一个单手导体绕组，没有内部接头，插入结构外壳中，对电磁负载做出反应。端子接头、外壳制造和真空浸渍系统等主要项目的开发是在供应商工厂进行批量生产之前的一个重要阶段。本文讨论了 CC 线圈的关键技术以及短样品原型制造的未来计划。
The Correction Coils system (CC) within ITER, is intended to reduce the range of magnetic error fields created by assembly or geometrical imperfections of the other coils used to confine, heat, and shape the plasma. The proposed magnet system consists of three sets of 6 coils each, located at the top (TCC), side (SCC) and bottom (BCC) of the Tokamak device and uses a NbTi cable-in-conduit superconducting conductor (CICC) operating at 4.2 K. The ITER Organization (IO) and the Institute of Plasma Physics at the Chinese Academy of Sciences (ASIPP) are jointly preparing the definition of the technical specifications and the upcoming qualification program for the Correction Coils. The proposed design consists of a one in hand conductor winding without internal joint inserted in a structural casing which reacts the electromagnetic loads. The development of major items such as terminal joints, casing manufacture, and vacuum impregnation system, is an essential phase before the series production which will take place at the premises of the supplier. This paper discusses the key technologies on CC coils and future plans for short sample prototypes fabrication.