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 |
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container_title | IEEE transactions on applied superconductivity |
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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 |
format | Article |
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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.</description><identifier>ISSN: 1051-8223</identifier><identifier>EISSN: 1558-2515</identifier><identifier>DOI: 10.1109/TASC.2010.2089954</identifier><identifier>CODEN: ITASE9</identifier><language>eng</language><publisher>New York, NY: IEEE</publisher><subject>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</subject><ispartof>IEEE transactions on applied superconductivity, 2011-06, Vol.21 (3), p.1960-1963</ispartof><rights>2015 INIST-CNRS</rights><rights>Copyright The Institute of Electrical and Electronics Engineers, Inc. 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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.</description><subject>Applied sciences</subject><subject>Coils</subject><subject>Conductors</subject><subject>Correction coils</subject><subject>Design. Technologies. Operation analysis. Testing</subject><subject>Electric connection. Cables. Wiring</subject><subject>Electrical engineering. Electrical power engineering</subject><subject>Electromagnets</subject><subject>Electronics</subject><subject>error fields</subject><subject>Exact sciences and technology</subject><subject>Insulation</subject><subject>Integrated circuits</subject><subject>ITER magnets</subject><subject>Joints</subject><subject>Plasmas</subject><subject>Semiconductor electronics. Microelectronics. Optoelectronics. Solid state devices</subject><subject>Testing. Reliability. 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Wiring</topic><topic>Electrical engineering. Electrical power engineering</topic><topic>Electromagnets</topic><topic>Electronics</topic><topic>error fields</topic><topic>Exact sciences and technology</topic><topic>Insulation</topic><topic>Integrated circuits</topic><topic>ITER magnets</topic><topic>Joints</topic><topic>Plasmas</topic><topic>Semiconductor electronics. Microelectronics. Optoelectronics. Solid state devices</topic><topic>Testing. Reliability. 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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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