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  1. 原著論文

Results of All ITER TF Full-Size Joint Sample Tests in Japan

https://repo.qst.go.jp/records/82683
https://repo.qst.go.jp/records/82683
09283938-aea7-42e7-b3f4-ae3d4a2a0f69
Item type 学術雑誌論文 / Journal Article(1)
公開日 2021-03-31
タイトル
タイトル Results of All ITER TF Full-Size Joint Sample Tests in Japan
言語
言語 eng
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_6501
資源タイプ journal article
アクセス権
アクセス権 metadata only access
アクセス権URI http://purl.org/coar/access_right/c_14cb
著者 Hideki, Kajitani

× Hideki, Kajitani

WEKO 1009698

Hideki, Kajitani

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Imagawa, Shinsaku

× Imagawa, Shinsaku

WEKO 1009699

Imagawa, Shinsaku

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Obana, Tetsuhiro

× Obana, Tetsuhiro

WEKO 1009700

Obana, Tetsuhiro

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Mio, Nakamoto

× Mio, Nakamoto

WEKO 1009701

Mio, Nakamoto

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Kunihiro, Matsui

× Kunihiro, Matsui

WEKO 1009702

Kunihiro, Matsui

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Norikiyo, Koizumi

× Norikiyo, Koizumi

WEKO 1009703

Norikiyo, Koizumi

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Masataka, Nakahira

× Masataka, Nakahira

WEKO 1009704

Masataka, Nakahira

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Hideki, Kajitani

× Hideki, Kajitani

WEKO 1009705

en Hideki, Kajitani

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Mio, Nakamoto

× Mio, Nakamoto

WEKO 1009706

en Mio, Nakamoto

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Kunihiro, Matsui

× Kunihiro, Matsui

WEKO 1009707

en Kunihiro, Matsui

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Norikiyo, Koizumi

× Norikiyo, Koizumi

WEKO 1009708

en Norikiyo, Koizumi

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Masataka, Nakahira

× Masataka, Nakahira

WEKO 1009709

en Masataka, Nakahira

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抄録
内容記述タイプ Abstract
内容記述 Nine toroidal field (TF) coils have been developed in Japan for the international thermonuclear experimental reactor (ITER). The joint resistance of TF coil should satisfy the requirement of smaller than 3 nano-ohm at 2 T of external magnetic field and 68 kA of transport current. Full-size joint sample (FSJS) tests were performed for joint development and for TF coil manufacture, as part of the process control. 11 FSJS tests are conducted in total. FSJS tests were conducted with assistance from a test faculty in the National Institute for Fusion Science as reported in a previous paper. All FSJS tests successfully satisfied the requirement of resistance less than 3 nΩ at 2 T. Additionally, the TF coil joints are subjected to cyclic electromagnetic force and warm-up/cool-down during the ITER operation. The authors investigated the joint performance for the above mentioned influence. The results showed no degradation in the joint resistance. Thus, the TF joint developed in Japan was qualified successfully.
書誌情報 IEEE Transactions on Applied Superconductivity

巻 31, 号 5, p. 4201905, 発行日 2021-03
出版者
出版者 IEEE
ISSN
収録物識別子タイプ ISSN
収録物識別子 1051-8223
DOI
識別子タイプ DOI
関連識別子 10.1109/TASC.2021.3064004
関連サイト
識別子タイプ DOI
関連識別子 https://doi.org/10.1109/TASC.2021.3064004
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