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Journal Articles

Neural-net predictor for beta limit disruptions in JT-60U

Yoshino, Ryuji

Nuclear Fusion, 45(11), p.1232 - 1246, 2005/11

 Times Cited Count:37 Percentile:74.07(Physics, Fluids & Plasmas)

Prediction of major disruptions observed at the $$beta$$-limit for tokamak plasmas has been investigated in JT-60U with developing neural networks. A sub-neural network is trained to output a value of the $$beta$$$$_{N}$$ limit every 2 ms. The target $$beta$$$$_{N}$$ limit is artificially set by the operator in the first step training and is modified in the second step training using the output $$beta$$$$_{N}$$ limit from the trained network. To improve the prediction performance further, the difference between the estimated $$beta$$$$_{N}$$ limit and the measured $$beta$$$$_{N}$$ and the other 11 parameters are inputted to a main neural network to calculate the stability level. Major disruptions have been predicted with a prediction success rate of 80% at 10 ms prior to the disruption while the false alarm rate is lower than 4%. This 80% is much higher than about 10% previously obtained. A prediction success rate of 90% has been also obtained with a false alarm rate of 12% at 10 ms prior to the disruption. This 12% is about a half of previously obtained one.

Journal Articles

Steady-state operation scenarios with a central current hole for JT-60SC

Tamai, Hiroshi; Ishida, Shinichi; Kurita, Genichi; Shirai, Hiroshi; Tsuchiya, Katsuhiko; Sakurai, Shinji; Matsukawa, Makoto; Sakasai, Akira

Fusion Science and Technology, 45(4), p.521 - 528, 2004/06

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

The 1.5D time-dependent transport analysis has been carried out to investigate steady state operation scenarios with a central current hole by off-axis current drive schemes consistent with a high bootstrap current fraction for a large superconducting tokamak JT-60SC. A steady state operation scenario with HH$$_{y2}$$=1.4 and $$beta$$$$_{N}$$=3.7 has been obtained at I$$_{p}$$=1.5 MA, B$$_{t}$$=2 T and q$$_{95}$$=5 where non-inductive currents are developed during the discharge to form a current hole with beam driven currents by tangential off-axis beams in combination with bootstrap currents by additional on-axis perpendicular beams. The bootstrap fraction increases up to nearly 75% of the plasma current and the current hole region is enlarged up to about 30% of the minor radius at 35 s from the discharge initiation. The current hole is confirmed to be sustained afterward for a long duration of 60 s. The stability analysis shows that the beta limit with the conducting wall can be about $$beta$$$$_{N}$$=4.5, which is substantially above the no wall ideal MHD limit.

Journal Articles

Neural-net disruption predictor in JT-60U

Yoshino, Ryuji

Nuclear Fusion, 43(12), p.1771 - 1786, 2003/12

 Times Cited Count:49 Percentile:79.65(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Ferromagnetic and resistive wall effects on the beta limit in a Tokamak

Kurita, Genichi; Tsuda, Takashi; Azumi, Masafumi; Ishida, Shinichi; Takeji, Satoru*; Sakasai, Akira; Matsukawa, Makoto; Ozeki, Takahisa; Kikuchi, Mitsuru

Nuclear Fusion, 43(9), p.949 - 954, 2003/09

 Times Cited Count:31 Percentile:67.25(Physics, Fluids & Plasmas)

In order to improve economic and environmental suitability of tokamak fusion reactors, both the accomplishment of high beta plasmas and the practical use of low activation materials to reduce the amount of radioactive waste are crucially important. Low radio-activation ferritic steel is considered as a most promising candidate for structural material in DEMO reactors, and there is the possibility of reduction of critical beta value by the deterioration of MHD stability due to ferromagnetism of ferritic steel. This paper investigates the effect of ferromagnetism with plasma flow on the beta limit of tokamak plasma by carrying out MHD stability analyses including ferromagnetic and plasma flow effects.

JAEA Reports

Development of measuring device for inner surfaces of embedded piping (Contract research)

Ito, Hirokuni*; Hatakeyama, Mutsuo*; Tachibana, Mitsuo; Yanagihara, Satoshi

JAERI-Tech 2003-012, 34 Pages, 2003/03

JAERI-Tech-2003-012.pdf:2.87MB

The MISE was developed to evaluate low-level radiological contaminations of inner surfaces of piping. The MISE consists of a cylindrically-formed double layered type detector and a piping crawling robot, which were designed and manufactured separately. In measurements of the contaminations, an outer cylindrical detector close to the surface of piping measures $$beta$$-rays and $$gamma$$-rays and an inner cylindrical detector set after a shielding plate for shield of $$beta$$-rays measures $$gamma$$-rays. The $$beta$$-ray counting rates are derived by subtracting $$gamma$$-ray counts measured by the inner detector from $$gamma$$- and $$beta$$-ray counts measured by the outer detector. The robot transports the double layered type detector with observing inner surfaces of piping. The detection limit for the contamination of $$^{60}$$Co was found to be about 0.17Bq/cm$$^{2}$$ with measurement time of 30 seconds. It is expected that 0.2Bq/cm$$^{2}$$ corresponding to clearance level of $$^{60}$$Co (0.4Bq/g) can be evaluated with measurement time of 2 seconds, which is equal to measurement speed of 54m/h.

Journal Articles

Magnetohydrodynamic stability of improved confinement plasmas in JT-60U

Takeji, Satoru; Isayama, Akihiko; Ozeki, Takahisa; Tokuda, Shinji; Ishii, Yasutomo; Oikawa, Toshihiro; Ishida, Shinichi; Kamada, Yutaka; Neyatani, Yuzuru; Yoshino, Ryuji; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.278 - 297, 2002/09

 Times Cited Count:7 Percentile:6.06(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Ideal/resistive modes analysis in reversed shear configuration plasmas

; Ishii, Yasutomo; ; Tokuda, Shinji; Ozeki, Takahisa; S.Hudson*; Kishimoto, Yasuaki

Chinese Physics Letters, 362, p.83 - 84, 1999/09

no abstracts in English

Journal Articles

ITER physics basis, 3; MHD stability, disruptional limits and disruptions

ITER Physics Expert Group on Disruptions, Plasma Control, and MHD

Nuclear Fusion, 39(12), p.2251 - 2389, 1999/00

no abstracts in English

JAEA Reports

Stability analysis of ITER plasmas with H-mode profiles

Tokuda, Shinji; Ozeki, Takahisa

JAERI-Research 94-030, 13 Pages, 1994/11

JAERI-Research-94-030.pdf:0.62MB

no abstracts in English

Journal Articles

Operational scenarios to avoid disruptions in JT-60U

Yoshino, Ryuji; Neyatani, Yuzuru; Isei, Nobuaki; Matsukawa, Makoto; Hosogane, Nobuyuki

Purazuma, Kaku Yugo Gakkai-Shi, 70(10), p.1081 - 1101, 1994/10

no abstracts in English

JAEA Reports

Stability analysis of external kink mode for ITER L-mode profile plasmas

Tokuda, Shinji; Ozeki, Takahisa

JAERI-Research 94-013, 16 Pages, 1994/09

JAERI-Research-94-013.pdf:0.66MB

no abstracts in English

Journal Articles

Observation of a fast beta collapse during high poloidal-beta discharges in JT-60

Ishida, Shinichi; Koide, Yoshihiko; Ozeki, Takahisa; Kikuchi, Mitsuru; Tsuji, Shunji; Shirai, Hiroshi; Naito, Osamu; Azumi, Masafumi

Physical Review Letters, 68(10), p.1531 - 1534, 1992/03

 Times Cited Count:54 Percentile:87.29(Physics, Multidisciplinary)

no abstracts in English

JAEA Reports

Operational limits and disruptions in tokamaks; Status and application to ITER

Tsunematsu, Toshihide; J.Hogan*; K.Borrass*; F.Engelmann*;

JAERI-M 89-056, 47 Pages, 1989/05

JAERI-M-89-056.pdf:1.25MB

no abstracts in English

Journal Articles

MHD stability analysis of tokamak plasmas with non ohmic currents

Tokuda, Shinji; Yamagiwa, Mitsuru; Tsunematsu, Toshihide; Takeda, Tatsuoki

Int. Conf. on Plasma Physics, p.925 - 928, 1989/00

no abstracts in English

JAEA Reports

Vectorization of MHD Equilibrium and Stability Codes

Nemoto, Toshiyuki; Tsunematsu, Toshihide

JAERI-M 87-062, 36 Pages, 1987/04

JAERI-M-87-062.pdf:0.79MB

no abstracts in English

JAEA Reports

Data set for Benchmark Calculation on Ideal MHD Beta Limit of INTOR Plasma

Tsunematsu, Toshihide; ; Nemoto, Toshiyuki; ; Takeda, Tatsuoki

JAERI-M 86-172, 54 Pages, 1986/10

JAERI-M-86-172.pdf:0.8MB

no abstracts in English

JAEA Reports

Characteristics of Pellet and Neutral-Beam Injected Single Null Divertor Discharges of the JFT-2M Tokamak

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

JAERI-M 86-148, 18 Pages, 1986/09

JAERI-M-86-148.pdf:0.57MB

no abstracts in English

JAEA Reports

Evaluation of Fusion Power Multiplication Factor

*; ;

JAERI-M 86-089, 46 Pages, 1986/06

JAERI-M-86-089.pdf:0.89MB

no abstracts in English

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

JAEA Reports

Beta-Limit of a Large Tokamak with a Circular Cross Section

Tsunematsu, Toshihide; Takeda, Tatsuoki; ; ; *; R.Gruber*; F.Troyon*

JAERI-M 9890, 16 Pages, 1982/01

JAERI-M-9890.pdf:0.37MB

no abstracts in English

JAEA Reports

Electromagnetic High-n Ballooning Instalilities

; *; ;

JAERI-M 9793, 40 Pages, 1981/11

JAERI-M-9793.pdf:0.98MB

no abstracts in English

21 (Records 1-20 displayed on this page)