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Shimada, Michiya; JT-60 Team
Plasma Physics and Controlled Nuclear Fusion Research 1992, Vol.1, p.57 - 77, 1993/09
Heating experiments have been carried out in JT-60U with plasma currents of up to 4 MA, toroidal fields of up to 4.2 T and a neutral beam heating power of 30 MW. Carbon fibre composite divertor plates with good alignment and bevelled edges provide an excellent power handling capability: no carbon burst has been observed during 5 s heating pulses at 20 MW. An H-mode was observed at the high toroidal field of 4.2 T. A confinement improvement factor of up to 1.6 over L-mode scaling has been obtained during the continuous ELMy phase at 4.2 T, for 2.7 MA and an injection power of 25 MW.
Ishida, Shinichi; Matsuoka, Mamoru; Kikuchi, Mitsuru; Tsuji, Shunji; Nishitani, Takeo; Koide, Yoshihiko; Ozeki, Takahisa; Fujita, Takaaki; Nakamura, Hiroo; Hosogane, Nobuyuki; et al.
Plasma Physics and Controlled Nuclear Fusion Research 1992, Vol.1, p.219 - 233, 1993/00
no abstracts in English
Kardaun, O.*; Ryter, F.*; Stroth, U.*; Kus, A.*; Deboo, J. C.*; Schissel, D. P.*; Bramson, G.*; Carlstrom, T. N.*; Thomsen, K.*; Campbell, D. J.*; et al.
Plasma Physics and Controlled Nuclear Fusion Research 1992, Vol.3, p.251 - 270, 1993/00
no abstracts in English
Watanabe, Kazuhiro; Hanada, Masaya; Inoue, Takashi; *; Mizuno, Makoto; Ohara, Yoshihiro; Okumura, Yoshikazu; Suzuki, Yasuo*; Tanaka, Hideki*; Tanaka, Masanobu*
Proc. of 14th Int. Conf. on Plasma Physics and Controlled Nuclear Fusion Research, p.371 - 378, 1993/00
no abstracts in English