Refine your search:     
Report No.
 - 
Search Results: Records 1-13 displayed on this page of 13
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Plasma profile control by using local heating and current drive with EC waves

Ikeda, Yoshitaka; Kubo, Shin*

Purazuma, Kaku Yugo Gakkai-Shi, 81(3), p.160 - 166, 2005/03

The local profile controls of electron temperature and current in fusion-oriented devices using the electron cyclotron (EC) wave is reviewed. Recent progress of the EC heating system that enabled those controls is briefly described. The specific feature of EC wave heating is local and high power density heating properties. Current drive and electron temperature profile control experiments using EC wave performed in order to improve and investigate plasma confinement properties are discussed.

Journal Articles

Intelligible seminor on fusion reactors, 3; Plasma heating system to generate high temperature fusion palsmas

Inoue, Takashi; Sakamoto, Keishi

Nippon Genshiryoku Gakkai-Shi, 47(2), p.120 - 127, 2005/02

no abstracts in English

Journal Articles

Accelerator R&D for JT-60U and ITER NB systems

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:19.19(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$$^{0}$$ 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.

Journal Articles

Neutral beam injectors for ITER and tokamak fusion reactors

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.

Journal Articles

Design of neutral beam system for ITER-FEAT

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:56 Percentile:3.52(Nuclear Science & Technology)

no abstracts in English

Journal Articles

ITER R&D: Auxiliary systems; Neutral beam heating and current drive system

Inoue, Takashi; Hemsworth, R. S.*; Kulygin, V.*; Okumura, Yoshikazu

Fusion Engineering and Design, 55(2-3), p.291 - 301, 2001/07

 Times Cited Count:20 Percentile:18.84(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutral beams for the International Thermonuclear Experimental Reactor

Inoue, Takashi; Di Pietro, E.*; Mondino, P. L.*; Bayetti, P.*; Hemsworth, R. S.*; Massmann, P.*; Fujiwara, Yukio; Hanada, Masaya; Miyamoto, Kenji; Okumura, Yoshikazu; et al.

Review of Scientific Instruments, 71(2), p.744 - 746, 2000/02

 Times Cited Count:17 Percentile:30.56(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Development of B$$_{4}$$C-carbon fiber composite ceramics as plasma facing materials in nuclear fusion reactor, 3; Heat resistance evaluation by electron beam irradiation and by in situ plasma discharge in JT-60

Jimbo, Ryutaro*; Saido, Masahiro; Nakamura, Kazuyuki; Akiba, Masato; ; Dairaku, Masayuki; *; *; *; *

Journal of the Ceramic Society of Japan, International Edition, 105, p.1179 - 1187, 1997/00

no abstracts in English

Journal Articles

Design and R&D of high power negative ion source/accelerator for ITER NBI

Inoue, Takashi; Okumura, Yoshikazu; Fujiwara, Yukio; Miyamoto, Kenji; Ohara, Yoshihiro; Miyamoto, Naoki*; Watanabe, Kazuhiro; B.Heinemann*; *

Fusion Technology 1996, 1, p.701 - 704, 1996/00

no abstracts in English

Journal Articles

Design analysis for reducing dose rate in the NBI to realize direct access by workers for a fusion experimental reactor

Inoue, Takashi; *; *; Yamashita, Y.*

Fusion Technology 1996, 0, p.1799 - 1802, 1996/00

no abstracts in English

Journal Articles

Development of high power negative ion sources and accelerators for neutral beam heating and current drive systems

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

Journal Articles

Effects of radio-frequency-induced radial diffusion on triton burnup

Yamagiwa, Mitsuru

Physics of Plasmas, 1(1), p.205 - 207, 1994/01

 Times Cited Count:4 Percentile:71.83(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Tokamak research at the Japan Atomic Energy Research Institute

Comments Plasma Phys.Controll.Fus., 26(1A), p.117 - 122, 1984/00

no abstracts in English

13 (Records 1-13 displayed on this page)
  • 1