Analysis of Contact Lengths of Strands with Cu Sleeves in CICC Joints

Cable-in-Conduit-Conductor (CICC) is used for the international thermonuclear fusion experimental reactor (ITER) toroidal field (TF) coils. But the critical current of the CICC is measured lower than expected one. This is partly explained by unbalanced current distribution caused by inhomogeneous co...

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Veröffentlicht in:	Plasma and Fusion Research 2012/10/15, Vol.7, pp.2403143-2403143
Hauptverfasser:	NAKAZAWA, Shinobu, ARAI, Daichi, MORIMURA, Toshiya, MIYAGI, Daisuke, TSUDA, Makoto, HAMAJIMA, Takataro, YAGAI, Tsuyoshi, NUNOYA, Yoshihiko, KOIZUMI, Norikiyo, TAKAHATA, Kazuya, OBANA, Tetsuhiro
Format:	Artikel
Sprache:	eng
Schlagworte:	cable-in-conduit conductor contact length joint twist pitch
Online-Zugang:	Volltext
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