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Journal Articles

Generation and termination of runaway electrons at major disruptions in JT-60U

Yoshino, Ryuji; Tokuda, Shinji; Kawano, Yasunori

Nuclear Fusion, 39(2), p.151 - 161, 1999/02

 Times Cited Count:137 Percentile:95.53(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

None

PNC TJ1612 97-001, 69 Pages, 1997/03

PNC-TJ1612-97-001.pdf:2.25MB

no abstracts in English

JAEA Reports

The Design study of the JT-60SU device, No.5; The Power supply for coils of JT-60SU

Aoyagi, Tetsuo; Nagashima, Keisuke; *; Mori, Katsuharu*; *; ; Kikuchi, Mitsuru;

JAERI-Research 97-010, 58 Pages, 1997/02

JAERI-Research-97-010.pdf:1.7MB

no abstracts in English

JAEA Reports

Plasma position control of ITER EDA plasma

Senda, Ikuo*; Nishio, Satoshi; Tsunematsu, Toshihide; *; Fujieda, Hirobumi*

JAERI-Tech 94-018, 56 Pages, 1994/09

JAERI-Tech-94-018.pdf:1.45MB

no abstracts in English

JAEA Reports

None

*; *

PNC TJ1216 93-003, 45 Pages, 1993/01

PNC-TJ1216-93-003.pdf:0.95MB

no abstracts in English

Journal Articles

Eddy current effect study on the JT-60 plasma equilibrium control

Kurihara, Kenichi

Fusion Engineering and Design, 19, p.235 - 257, 1992/00

 Times Cited Count:5 Percentile:48.18(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Advanced control of the tokamak plasma shape and position by the quick responce power supply

*; *; *; Matsuzaki, Yoshimi; ; ; *; *

Fusion Technology,1988, Vol.1, p.674 - 678, 1989/00

no abstracts in English

JAEA Reports

Conceptual design study of fusion experimental reactor, FY 86 year; Plasma current, Position and shape control

*; *; *; *; Fujisawa, Noboru

JAERI-M 87-112, 38 Pages, 1987/08

JAERI-M-87-112.pdf:1.19MB

no abstracts in English

JAEA Reports

Conceptual Design Study of Quasi-Steady State Fusion Experimental Reactor (FER-Q) Part 2

; Tone, Tatsuzo; ; ; ; ; ; ; ; ; et al.

JAERI-M 85-178, 872 Pages, 1985/12

JAERI-M-85-178.pdf:19.66MB

no abstracts in English

JAEA Reports

Japanese Contributions to IAEA INTOR Workshop, Phase IIA; Chapte X:Electromagnetics

; *; *; ; *; *; ; *; *

JAERI-M 82-177, 78 Pages, 1982/11

JAERI-M-82-177.pdf:1.5MB

no abstracts in English

JAEA Reports

Japanese Contributions to IAEA INTOR Workshop,Phase IIA; Chapter IV:Plasma Confinement and Control

*; ; *; ; ; Sengoku, Seio; ; ; ; ; et al.

JAERI-M 82-171, 45 Pages, 1982/11

JAERI-M-82-171.pdf:0.92MB

no abstracts in English

JAEA Reports

Study of Equilibrium and Axisymmetric Stability of Dee-Shaped Plasmas in Doublet III

; ; ; N.H.Brooks*; R.P.Seraydarian*; *; ; Yoshida, H.; *; *; et al.

JAERI-M 9698, 29 Pages, 1981/09

JAERI-M-9698.pdf:0.69MB

no abstracts in English

JAEA Reports

JAEA Reports

Journal Articles

Tokamak circuit

; ; ; *;

Japanese Journal of Applied Physics, 16(12), p.2237 - 2244, 1977/12

 Times Cited Count:14

no abstracts in English

Journal Articles

Experimental study on control of radiation polymerization by dose rate regulation

; Kawakami, Waichiro; *

Ind.Eng.Chem.,Prod.Des.Dev., 15(4), p.549 - 552, 1976/04

no abstracts in English

Oral presentation

Analysis of plasma position control for Broader Approach (BA) DEMO reactor

Takase, Haruhiko; Tobita, Kenji; Sakamoto, Yoshiteru; Uto, Hiroyasu; Mori, Kazuo; Kudo, Tatsuya

no journal, , 

Analysis of plasma position control is one of important issues for design of DEMO reactor on Broader Approach (BA). Especially, plasma performance, blanket design and maintenance scheme influence the plasma position control mutually. Therefore, we made a numerical simulation code that consists of plasma equilibrium analysis, eddy current analysis and plasma motion analysis. Since we analyzed several cases of design using this numerical simulation code, the results will be shown.

Oral presentation

Analysis of plasma position control for DEMO reactor

Takase, Haruhiko; Uto, Hiroyasu; Sakamoto, Yoshiteru; Mori, Kazuo; Kudo, Tatsuya; Tobita, Kenji

no journal, , 

Pre-conceptual design of DEMO reactor has been preceded under collaboration Japan and Europe (Broader Approach activities (BA)). In the case of DEMO reactor, it is important for design of plasma position control to take into account the actual shape of vacuum vessel and in-vessel components precisely since the design condition of DEMO reactor is different from current tokamak devices and ITER (for example, installation of maintenance ports). To consider the DEMO design condition, the numerical simulation that consists of three modules has been developed. As results, (1) The time constants of eddy current in the breeding blankets are less than 10ms and there is no influence to passive stabilization effect. (2) The stabilization effect of conducting components decreases by considering installation of vertical maintenance port. The adoption of vertical port is related to the choice of the maintenance scenario.

Oral presentation

Analysis of plasma position control for DEMO reactor

Takase, Haruhiko; Uto, Hiroyasu; Sakamoto, Yoshiteru; Mori, Kazuo; Kudo, Tatsuya; Hiwatari, Ryoji; Tobita, Kenji

no journal, , 

Plasma position control for DEMO reactor has been studied using numerical simulation, which consists of plasma equilibrium, eddy current and active feedback control analyses. The stabilization effect of in-vessel components, the influence on the magnetic detector and the power of active feedback control coils are evaluated. Especially, the influence on plasma position control by installation of the breeding blanket modules is shown in this paper.

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