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Journal Articles

Heating, current drive, and advanced plasma control in JFT-2M

Hoshino, Katsumichi; Yamamoto, Takumi; Tamai, Hiroshi; Oasa, Kazumi; Kawashima, Hisato; Miura, Yukitoshi; Ogawa, Toshihide; Shoji, Teruaki*; Shibata, Takatoshi; Kikuchi, Kazuo; et al.

Fusion Science and Technology, 49(2), p.139 - 167, 2006/02

 Times Cited Count:2 Percentile:17.18(Nuclear Science & Technology)

The main results obtained by the various heating and current drive systems, external coil system and divertor bias system are reviewed from the viewpoint of the advanced active control of the tokamak plasma. Also, the features of each system are described. The contribution of the JFT-2M in these areas are summarized.

Journal Articles

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

Inoue, Takashi; Sakamoto, Keishi

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

no abstracts in English

Journal Articles

Heating and current drive by N-NBI in JT-60U and LHD

Kaneko, Osamu*; Yamamoto, Takumi; Akiba, Masato; Hanada, Masaya; Ikeda, Katsunori*; Inoue, Takashi; Nagaoka, Kenichi*; Oka, Yoshihide*; Osakabe, Masaki*; Takeiri, Yasuhiko*; et al.

Fusion Science and Technology, 44(2), p.503 - 507, 2003/09

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

High energy negative-ion-based neutral beam injection (N-NBI) is expected as an efficient and reliable tool of heating and current driving for reactor plasmas such as ITER. A world wide activity on developing technology of negative ion production and beam formation started in 1980's and the great progress has been achieved up to now. In particular, Japan has two large projects that planned adopting N-NBI for real plasma experiments; the JT-60U tokamak and the LHD heliotron, which further motivated the R&D activity. These R&D programs were carried out at JAERI and NIFS separately in Japan, and both were successfully done. The first beam injection experiment was made on the JT-60U in 1996, followed by the LHD in 1998. They were the first experiments on heating plasma by high energy beam in tokamaks and in stellerators, and the obtained results were very promising.

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:64 Percentile:96.61(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:67.92(Instruments & Instrumentation)

no abstracts in English

Journal Articles

ITER physics basis, 6; Plasma auxiliary heating and current drive

ITER Physics Expert Group on Energetic Particles, Heating and Current Drive

Nuclear Fusion, 39(12), p.2495 - 2539, 1999/00

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

JAEA Reports

Shielding analysis of the ITER/EDA NBI duct

S.Zimin*; *; Takatsu, Hideyuki; Sato, Satoshi; Tsunematsu, Toshihide; Inoue, Takashi; Ohara, Yoshihiro

JAERI-Tech 94-015, 37 Pages, 1994/08

JAERI-Tech-94-015.pdf:0.92MB

no abstracts in English

Journal Articles

Study of combined NBI and ICRF enhancement of the D-$$^{3}$$He fusion yield with a Fokker-Planck code

Yamagiwa, Mitsuru; Kishimoto, Yasuaki; Fujii, Tsuneyuki; Kimura, Haruyuki

Nuclear Fusion, 33(3), p.493 - 500, 1993/00

 Times Cited Count:6 Percentile:32.18(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Vectorization and improvement of nuclear codes; MEUDAS4, FORCE, STREAM V2.6, HEATING7-VP, SCDAP/RELAP5/MOD2.5, NBI3DGFN

*; *; *; *; *; Yokokawa, Mitsuo

JAERI-M 92-142, 117 Pages, 1992/09

JAERI-M-92-142.pdf:2.45MB

no abstracts in English

Journal Articles

D-$$^{3}$$He fusion yield with higher harmonic ICRF heating of $$^{3}$$He beams

Yamagiwa, Mitsuru; Kimura, Haruyuki

Nuclear Fusion, 31(8), p.1519 - 1526, 1991/00

 Times Cited Count:4 Percentile:28.62(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

D-He$$^{3}$$ fusion yield in higher harmonic ICRF heated plasma

Yamagiwa, Mitsuru; Kimura, Haruyuki; Takizuka, Tomonori; Fujii, Tsuneyuki

Proc. of the 17th EPS Conf. on Controlled Fusion and Plasma Heating, p.1007 - 1010, 1990/00

no abstracts in English

JAEA Reports

Transport Analysis of OH and NBI Heated Discharges in JT-60

; ; ; ; JT-60 Team

JAERI-M 87-029, 30 Pages, 1987/03

JAERI-M-87-029.pdf:0.87MB

no abstracts in English

JAEA Reports

JAEA Reports

Japanese Contributions to IAEA INTOR Workshop,Phase Two A,Part 2 Chapter VIII:Physics

Takeda, Tatsuoki; ; ; ; ; *; ; *; ;

JAERI-M 85-080, 70 Pages, 1985/07

JAERI-M-85-080.pdf:2.42MB

no abstracts in English

19 (Records 1-19 displayed on this page)
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