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Inoue, Takashi; Hanada, Masaya; Iga, Takashi*; Imai, Tsuyoshi; Kashiwagi, Mieko; Kawai, Mikito; Morishita, Takatoshi; Taniguchi, Masaki; Umeda, Naotaka; Watanabe, Kazuhiro; et al.
Fusion Engineering and Design, 66-68, p.597 - 602, 2003/09
Times Cited Count：21 Percentile：77.61(Nuclear Science & Technology)The neutral beam (NB) injection has been one of the most promising methods for plasma heating and current drive in tokamak fusion devices. JAERI has developed high energy electrostatic accelerators for the NB systems in JT-60U and ITER. Recent progress on this R&D are as follows: 1) In the JT-60U NB system, some of the beams has been deflected due to distorted electric field in the accelerator, resulting in an excess heat load on the NB port. By correcting the electric field, a continuous injection of H
beam was succeeded for 10 s with the NB power of 2.6 MW at 355 keV. 2) To increase the beam energy, a metal structure called stress ring was designed. The ring reduces electric field concentration at the triple junction point (interface between metal and dielectric insulator inside vacuum). Initial test of the accelerators with the stress rings has shown higher voltage hold off performance in both accelerators for JT-60U and ITER R&D than that without rings.
Inoue, Takashi
Purazuma, Kaku Yugo Gakkai-Shi, 78(5), p.398 - 404, 2002/05
Neutral beam (NB) heating and current drivesystem for ITER fires the energetic particle beams of 1 MeV, 33 MW (16.5 MW/NB injector) into the fusion plasma. The design allows late installation of third NB injector for upgrade in current drive experiment toward steady state operation. The ITER NB system has been designed to fulfill requirements of the plasma physics, including advanced scenario achieved with off-axis current drive by NB. A design overview of the ITER NB system is described. The paper also reports recent R&D status of ion source and accelerator, as key components of the NB system, toward ITER construction. NB heating and current drive performance required in future tokamak reactors are discussed together with the necessary R&D issues.
Inoue, Takashi; Di Pietro, E.*; Hanada, Masaya; Hemsworth, R. S.*; Krylov, A.*; Kulygin, V.*; Massmann, P.*; Mondino, P. L.*; Okumura, Yoshikazu; Panasenkov, A.*; et al.
Fusion Engineering and Design, 56-57, p.517 - 521, 2001/10
Times Cited Count：64 Percentile：96.43(Nuclear Science & Technology)no abstracts in English
Inoue, Takashi; Hanada, Masaya; Kuriyama, Masaaki; ; Matsuoka, Mamoru; Miyamoto, Kenji; Ohara, Yoshihiro; Okumura, Yoshikazu; Watanabe, Kazuhiro
IAEA-CN-60/F-10, 0, p.687 - 693, 1995/00
no abstracts in English
Kondoh, Takashi; JT-60 Team
Physics of Plasmas, 1(5), p.1489 - 1496, 1994/05
Times Cited Count：19 Percentile：56.80(Physics, Fluids & Plasmas)no abstracts in English
Inoue, Takashi; Miyamoto, Kenji; Mizuno, Makoto; Okumura, Yoshikazu; Ohara, Yoshihiro; G.D.Ackerman*; C.F.Chan*; W.S.Cooper*; J.W.Kwan*; M.C.Vella*
15th IEEE/NPSS Symp. on Fusion Engineering,Vol. 1, 0, p.474 - 477, 1994/00
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
Tanaka, Shigeru; Ohara, Yoshihiro; Yamamoto, Shin
Fusion Technology, 91(3), p.531 - 539, 1991/05
no abstracts in English
; Yamamoto, Shin; Sugihara, Masayoshi; Fujisawa, Noboru
JAERI-M 87-209, 45 Pages, 1988/01
no abstracts in English
Horiike, Hiroshi; Ohara, Yoshihiro; Okumura, Yoshikazu; Shibata, Takemasa; Tanaka, Shigeru
JAERI-M 86-064, 140 Pages, 1986/04
no abstracts in English
