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Journal Articles

Critical $$beta$$ analyses with ferromagnetic and plasma rotation effects and wall geometry for a high $$beta$$ steady state tokamak

Kurita, Genichi; Bialek, J.*; Tsuda, Takashi; Azumi, Masafumi*; Ishida, Shinichi; Navratil, G. A.*; Sakurai, Shinji; Tamai, Hiroshi; Matsukawa, Makoto; Ozeki, Takahisa; et al.

Nuclear Fusion, 46(2), p.383 - 390, 2006/02

 Times Cited Count:9 Percentile:31.08(Physics, Fluids & Plasmas)

It is shown that critical beta is decreased by ferromagnetic effect by about 8% for $$mu$$/$$mu$$$$_{0}$$$$sim$$2, $$mu$$ and $$mu$$$$_{0}$$ denoting the permeability of ferromagnetic wall and vacuum, respectively, for tokamak of aspect ratio 3. The existence of the stability window for resistive wall mode opened by both effects of the toroidal plasma rotation and the plasma dissipation, which was not observed for high aspect ratio tokamak, is found for tokamak of aspect ratio 3. The effect of ferromagnetism on them is also investigated. The critical beta analyses of NCT (National Centralized Tokamak) plasma using VALEN code are started with stabilizing plate and vacuum vessel geometry with finite resistivity, and the results for passive effect of stabilizing plate are obtained. The calculations including stabilizing effect of the vacuum-vessel and also active feedback control are also performed for present design of NCT plasma.

Journal Articles

Overview of JT-60U diagnostics for reactor-relevant plasma physics

Hatae, Takaki; JT-60 Team

Proceedings of 6th Japan-Australia Workshop on Plasma Diagnostics (CD-ROM), 16 Pages, 2002/00

The diagnostic system of JT-60U is composed of about 50 individual diagnostic devices. Recently, the detailed radial profile measurements of plasma parameters such as electron temperature, electron density, ion temperature, plasma rotation, and plasma current (safety factor q) have been improved. As a result, the understanding of internal structure of plasmas has advanced. In particular, detailed studies of the internal transport barrier could be performed in reversed magnetic shear plasmas. Furthermore, a "current hole" or a nearly zero current density at the plasma center was discovered in JT-60U plasmas by using a motional stark effect (MSE) system. Several diagnostic signal have been linked to actuators such as neutral beam injectors, the gas feed system, and the electron cyclotron heating system establishing the real-time control of electron temperature, neutron yield, radiated power, and electron temperature gradient, and thus improving plasma performance.

JAEA Reports

Test program for reactor control system in rise-to-power test in HTTR

Nakagawa, Shigeaki; Saito, Kenji; Homma, Fumitaka; Tachibana, Yukio; Kunitomi, Kazuhiko

JAERI-Tech 2000-009, p.88 - 0, 2000/02

JAERI-Tech-2000-009.pdf:6.19MB

no abstracts in English

Journal Articles

Remote handling test and full-scale equipment development for ITER blanket maintenance

Nakahira, Masataka; Kakudate, Satoshi; Oka, Kiyoshi; ; ; Tada, Eisuke; ; Shibanuma, Kiyoshi; R.Haange*

Proceedings of 17th IEEE/NPSS Symposium Fusion Engineering (SOFE'97), 2, p.929 - 932, 1998/00

no abstracts in English

Journal Articles

JT-60U plasma control system

Kimura, Toyoaki; Kurihara, Kenichi; Kawamata, Yoichi; Akiba, K.*; ; Terakado, Tsunehisa; Yoshino, Ryuji

Fusion Technology, 32(3), p.404 - 415, 1997/11

no abstracts in English

Journal Articles

Feedback control of neutron emission rate in JT-60U

Neyatani, Yuzuru; Fukuda, Takeshi; Nishitani, Takeo; Yoshino, Ryuji; Kawamata, Yoichi; Sakata, Shinya; Saito, Naoyuki; Kimura, Toyoaki

Fusion Engineering and Design, 36(2-3), p.429 - 433, 1997/05

 Times Cited Count:12 Percentile:67.87(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Atmospheric-pressure small-scale thermal-hydraulic experiment of a PIUS-type reactor

; ; ; ; Anoda, Yoshinari; Murata, Hideo; Kukita, Yutaka

Journal of Nuclear Science and Technology, 29(12), p.1152 - 1161, 1992/12

no abstracts in English

JAEA Reports

JT-60 upgrade vertical stability experiments and analysis

D.A.Humphreys*; Yoshino, Ryuji

JAERI-M 92-069, 25 Pages, 1992/05

JAERI-M-92-069.pdf:0.87MB

no abstracts in English

Journal Articles

Plasma feedback control system design and the results of JT-60U

Matsukawa, Makoto; Ninomiya, Hiromasa; Horiike, Hiroshi; Hosogane, Nobuyuki; Yoshino, Ryuji

Fusion Technology, 21(3), p.1624 - 1629, 1992/05

no abstracts in English

Journal Articles

Thermal-hydraulic experiment for safe and stable operation of a PIUS-type reactor

; ; ; I.D.Irianto*; ; ; Anoda, Yoshinari; Murata, Hideo; Kukita, Yutaka

Proc. of the Int. Conf. on Design and Safety of Advanced Nuclear Power Plants,Vol. 2, p.17.6-1 - 17.6-6, 1992/00

no abstracts in English

JAEA Reports

JAEA Reports

Vertical Position Control of the Elongated INTOR Plasma

; ; ; ; ;

JAERI-M 82-213, 38 Pages, 1983/01

JAERI-M-82-213.pdf:0.81MB

no abstracts in English

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