From Design to Development Phase of the ITER Correction Coils

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 to...

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Veröffentlicht in:IEEE transactions on applied superconductivity 2011-06, Vol.21 (3), p.1960-1963
Hauptverfasser: Foussat, A, Dolgetta, N, Jong, C, Libeyre, P, Mitchell, N, Weiyue Wu, Liping Liu, Shuangsong Du, Xufeng Liu, Xiaowu Yu, Shiqiang Han, Jing Wei
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container_end_page 1963
container_issue 3
container_start_page 1960
container_title IEEE transactions on applied superconductivity
container_volume 21
creator Foussat, A
Dolgetta, N
Jong, C
Libeyre, P
Mitchell, N
Weiyue Wu
Liping Liu
Shuangsong Du
Xufeng Liu
Xiaowu Yu
Shiqiang Han
Jing Wei
description 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.
doi_str_mv 10.1109/TASC.2010.2089954
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source IEEE Electronic Library (IEL)
subjects Applied sciences
Coils
Conductors
Correction coils
Design. Technologies. Operation analysis. Testing
Electric connection. Cables. Wiring
Electrical engineering. Electrical power engineering
Electromagnets
Electronics
error fields
Exact sciences and technology
Insulation
Integrated circuits
ITER magnets
Joints
Plasmas
Semiconductor electronics. Microelectronics. Optoelectronics. Solid state devices
Testing. Reliability. Quality control
Various equipment and components
Welding
Windings
title From Design to Development Phase of the ITER Correction Coils
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