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JAEA Reports

Research and development plan of fusion technologies in JAERI toward DEMO reactors

Department of Fusion Engineering Research

JAERI-Review 2005-011, 139 Pages, 2005/03

JAERI-Review-2005-011.pdf:11.95MB

no abstracts in English

Journal Articles

Formation of a charge-exchange target for fast ions in the plasma of large-scale toroidal devices under NBI conditions

Mironov, M. I.*; Khudoleev, A. V.*; Kusama, Yoshinori

Plasma Physics Reports, 30(2), p.164 - 168, 2004/02

 Times Cited Count:0 Percentile:0.02(Physics, Fluids & Plasmas)

High-energy charge-exchange diagnostics can determine the distribution function of fast atoms produced via the neutralization of hydrogen ions by hydrogen-like impurity ions. Deriving the distribution function requires to know the composition and spatial distribution of the target ions in a plasma. A charge-exchange target forms as a result of the interaction between impurity nuclei and beam atoms. Depending on the arrangement of heating beams with respect to the diagnostics, it is necessary to calculate their trajectories. A model which takes into account elementary processes resulting in the ionization equilibrium of the ions of impurities in a specific tokamak configuration is proposed. The model is applied to the JT-60U plasma. Mechanisms for the formation of charge-exchange atomic flows are considered. The relative contributions of different heating injectors to the charge-exchange flow are estimated. Based on the calculated results, a method is proposed for local measurements of the ion distribution function with a stationary analyzer.

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:78.43(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:64 Percentile:96.58(Nuclear Science & Technology)

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

High power negative ion beam development for heating and current drive in fusion plasmas

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

Journal Articles

Anomalous ion transport of L-mode plasmas in JT-60

Hirayama, Toshio; Shirai, Hiroshi; Yagi, Masatoshi; Shimizu, Katsuhiro; Koide, Yoshihiko; Kikuchi, Mitsuru; Azumi, Masafumi

Nuclear Fusion, 32(1), p.89 - 106, 1992/00

 Times Cited Count:7 Percentile:33.03(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Local transport analysis of L-mode plasmas in JT-60 tokamak

Hirayama, Toshio; Kikuchi, Mitsuru; Shirai, Hiroshi; Shimizu, Katsuhiro; Yagi, Masatoshi; Koide, Yoshihiko; Ishida, Shinichi; Azumi, Masafumi

JAERI-M 91-026, 28 Pages, 1991/03

JAERI-M-91-026.pdf:1.01MB

no abstracts in English

Journal Articles

Neutral beam injection system for JT-60

;

Nihon Genshiryoku Gakkai-Shi, 28(5), p.376 - 383, 1986/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Plasma heating by multiple-short-pulse neutral beams

; ; *; *

Plasma Physics and Controlled Nuclear Fusion Research 1984, Vol.l, p.665 - 672, 1985/00

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

Journal Articles

Plasma shapes for achieving high heating efficiency during neutral beam injection in doublet III

; ; ; *; ; *; ; ; ; ; et al.

Japanese Journal of Applied Physics, 23(5), p.L316 - L318, 1984/00

 Times Cited Count:4 Percentile:32.26(Physics, Applied)

no abstracts in English

Journal Articles

Tapered tungsten filament for a long life cathode

; Ohara, Yoshihiro

Review of Scientific Instruments, 55(10), p.1625 - 1631, 1984/00

 Times Cited Count:4 Percentile:59.6(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

JFT-2 Tokamak Neutral Injector and Preliminary Results of Additional Heating Experiment

*; *; ; ; ; ; ; ; *; ; et al.

JAERI-M 7043, 27 Pages, 1977/04

JAERI-M-7043.pdf:0.58MB

no abstracts in English

Journal Articles

Effect of the finite size electrode on the beam divergence of an intense ion source for the thermonuclear fusion research

Matsuda, Shinzaburo

Japanese Journal of Applied Physics, 13(10), p.1630 - 1635, 1974/10

 Times Cited Count:3

no abstracts in English

16 (Records 1-16 displayed on this page)
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