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

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

Bi-2223, current lead, heat exchanger, NbTi
1051-8223
DIng, Kaizhong
c5a812dd-39d5-4dab-bf31-fa1e1ba1225a
Zhou, Tingzhi
ece34deb-322f-4951-bc3e-6627cd9bbca6
Ballarino, Amalia
8fad5237-02dc-45c3-89c7-ce67ce7cae8c
Gung, Chenyu
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Lu, Kun
05a1bcb8-2849-4df8-90fe-53412e323db4
Song, Yuntao
a71c5483-907c-40de-92c6-ac61494f1c57
Niu, Erwu
f24f11d8-c320-4fee-bbcc-e92e66deaf8a
Bauer, Pierre
43cca7e7-4805-4f3a-8b67-0e21dccc4f3d
Devred, Arnaud
b64ae9a2-4960-471c-89f5-cebceb90a8af
Lee, Seungje
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Fernandez, Antonio Vergara
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Taylor, Thomas
1a05c484-c420-4c90-b822-0dc0aa51f8e0
Yang, Yifeng
4cac858a-e0c0-4174-a839-05ca394fc51f
DIng, Kaizhong
c5a812dd-39d5-4dab-bf31-fa1e1ba1225a
Zhou, Tingzhi
ece34deb-322f-4951-bc3e-6627cd9bbca6
Ballarino, Amalia
8fad5237-02dc-45c3-89c7-ce67ce7cae8c
Gung, Chenyu
08fe2c95-83b9-4375-9b2e-e5eed0500af2
Lu, Kun
05a1bcb8-2849-4df8-90fe-53412e323db4
Song, Yuntao
a71c5483-907c-40de-92c6-ac61494f1c57
Niu, Erwu
f24f11d8-c320-4fee-bbcc-e92e66deaf8a
Bauer, Pierre
43cca7e7-4805-4f3a-8b67-0e21dccc4f3d
Devred, Arnaud
b64ae9a2-4960-471c-89f5-cebceb90a8af
Lee, Seungje
13658e4f-d284-4fc0-8aaf-24059fd78917
Fernandez, Antonio Vergara
9a5c4cab-5dad-4152-849f-6b25e0b86c13
Taylor, Thomas
1a05c484-c420-4c90-b822-0dc0aa51f8e0
Yang, Yifeng
4cac858a-e0c0-4174-a839-05ca394fc51f

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 and Yang, Yifeng (2019) Manufacture and Test of the ITER TF Type HTS Current Lead Prototypes. IEEE Transactions on Applied Superconductivity, 29 (5), [8638577]. (doi:10.1109/TASC.2019.2898517).

Record type: Article

Abstract

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.

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More information

Accepted/In Press date: 15 January 2019
e-pub ahead of print date: 11 February 2019
Published date: 1 August 2019
Keywords: Bi-2223, current lead, heat exchanger, NbTi

Identifiers

Local EPrints ID: 434177
URI: http://eprints.soton.ac.uk/id/eprint/434177
ISSN: 1051-8223
PURE UUID: ff6a724c-5705-4d4f-b230-a1bae949ed5f
ORCID for Yifeng Yang: ORCID iD orcid.org/0000-0002-3874-6735

Catalogue record

Date deposited: 13 Sep 2019 16:30
Last modified: 10 Nov 2021 02:43

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Contributors

Author: Kaizhong DIng
Author: Tingzhi Zhou
Author: Amalia Ballarino
Author: Chenyu Gung
Author: Kun Lu
Author: Yuntao Song
Author: Erwu Niu
Author: Pierre Bauer
Author: Arnaud Devred
Author: Seungje Lee
Author: Antonio Vergara Fernandez
Author: Thomas Taylor
Author: Yifeng Yang ORCID iD

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