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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...
Autores principales: | , , , , , , , , , , , , |
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Lenguaje: | eng |
Publicado: |
2019
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Materias: | |
Acceso en línea: | https://dx.doi.org/10.1109/TASC.2019.2898517 http://cds.cern.ch/record/2686983 |
_version_ | 1780963614777147392 |
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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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