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Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes

High temperature superconducting current leads (HTS-CL) are designed to supply the current to the large superconducting ITER magnets for the operation with reduced heat load to the cryogenic system. The Toroidal field (TF) current leads are the largest with a current capacity of 68 kA each. The Inst...

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Autores principales: Ding, Kaizhong, Zhou, Tingzhi, Ballarino, Amalia, Gung, Chenyu, Lu, Kun, Song, Yuntao, Niu, Erwu, Bauer, Pierre, Devred, Arnaud, Lee, Seungje, Fernandez, Antonio Vergara, Taylor, Thomas, Yang, Yifeng
Lenguaje:eng
Publicado: 2019
Materias:
Acceso en línea:https://dx.doi.org/10.1109/TASC.2019.2898517
http://cds.cern.ch/record/2686983
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author Ding, Kaizhong
Zhou, Tingzhi
Ballarino, Amalia
Gung, Chenyu
Lu, Kun
Song, Yuntao
Niu, Erwu
Bauer, Pierre
Devred, Arnaud
Lee, Seungje
Fernandez, Antonio Vergara
Taylor, Thomas
Yang, Yifeng
author_facet Ding, Kaizhong
Zhou, Tingzhi
Ballarino, Amalia
Gung, Chenyu
Lu, Kun
Song, Yuntao
Niu, Erwu
Bauer, Pierre
Devred, Arnaud
Lee, Seungje
Fernandez, Antonio Vergara
Taylor, Thomas
Yang, Yifeng
author_sort Ding, Kaizhong
collection CERN
description High temperature superconducting current leads (HTS-CL) are designed to supply the current to the large superconducting ITER magnets for the operation with reduced heat load to the cryogenic system. The Toroidal field (TF) current leads are the largest with a current capacity of 68 kA each. The Institute of Plasma Physics of the Chinese Academy of Sciences (ASIPP) is responsible for the supply of the current leads based on a design jointly developed with the ITER organization. Before the supply of the TF HTS-CL series, a pair of prototypes was manufactured in 2014 by ASIPP and associated manufacturers according to previously qualified manufacturing procedures. Rigorous quality control measures were developed and applied in preparation for series manufacturing. To verify compliance of the prototypes with the ITER specification, thorough testing was conducted in 2015. The test items under particular scrutiny were: the pressure drop in the counter-flow heat exchanger, the loss of flow accident test after steady state operation at 68 kA current, the so-called overheating time of the HTS module following an induced quench, the electrical resistances of the soldered joints inside the lead assembly (i.e., the low temperature superconducting (LTS) to busbar and the HTS to LTS joints), and the conduction heat load per lead to the 4.5 K end. In this paper, the main manufacturing steps are discussed, and test results are presented and discussed.
id oai-inspirehep.net-1746852
institution Organización Europea para la Investigación Nuclear
language eng
publishDate 2019
record_format invenio
spelling oai-inspirehep.net-17468522019-09-30T06:29:59Zdoi:10.1109/TASC.2019.2898517http://cds.cern.ch/record/2686983engDing, KaizhongZhou, TingzhiBallarino, AmaliaGung, ChenyuLu, KunSong, YuntaoNiu, ErwuBauer, PierreDevred, ArnaudLee, SeungjeFernandez, Antonio VergaraTaylor, ThomasYang, YifengManufacture and Test of the ITER TF Type HTS Current Lead PrototypesAccelerators and Storage RingsHigh temperature superconducting current leads (HTS-CL) are designed to supply the current to the large superconducting ITER magnets for the operation with reduced heat load to the cryogenic system. The Toroidal field (TF) current leads are the largest with a current capacity of 68 kA each. The Institute of Plasma Physics of the Chinese Academy of Sciences (ASIPP) is responsible for the supply of the current leads based on a design jointly developed with the ITER organization. Before the supply of the TF HTS-CL series, a pair of prototypes was manufactured in 2014 by ASIPP and associated manufacturers according to previously qualified manufacturing procedures. Rigorous quality control measures were developed and applied in preparation for series manufacturing. To verify compliance of the prototypes with the ITER specification, thorough testing was conducted in 2015. The test items under particular scrutiny were: the pressure drop in the counter-flow heat exchanger, the loss of flow accident test after steady state operation at 68 kA current, the so-called overheating time of the HTS module following an induced quench, the electrical resistances of the soldered joints inside the lead assembly (i.e., the low temperature superconducting (LTS) to busbar and the HTS to LTS joints), and the conduction heat load per lead to the 4.5 K end. In this paper, the main manufacturing steps are discussed, and test results are presented and discussed.oai:inspirehep.net:17468522019
spellingShingle Accelerators and Storage Rings
Ding, Kaizhong
Zhou, Tingzhi
Ballarino, Amalia
Gung, Chenyu
Lu, Kun
Song, Yuntao
Niu, Erwu
Bauer, Pierre
Devred, Arnaud
Lee, Seungje
Fernandez, Antonio Vergara
Taylor, Thomas
Yang, Yifeng
Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes
title Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes
title_full Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes
title_fullStr Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes
title_full_unstemmed Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes
title_short Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes
title_sort manufacture and test of the iter tf type hts current lead prototypes
topic Accelerators and Storage Rings
url https://dx.doi.org/10.1109/TASC.2019.2898517
http://cds.cern.ch/record/2686983
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