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Kudo, Yusuke; Sawai, Tomotsugu; Sakurai, Shinji; Masaki, Kei; Suzuki, Yutaka; Sasajima, Tadayuki; Hayashi, Takao; Takahashi, Ryukichi*; Honda, Masao; Jitsukawa, Shiro; et al.
Journal of the Korean Physical Society, 49(96), p.S297 - S301, 2006/12
Installation of ferritic steel tiles was proposed in JT-60U to reduce the toroidal magnetic field ripple and to improve the fast ion loss, which degrades heating efficiency and increases heat load on plasma facing component under large volume plasma operations. We selected a 8Cr-2W-0.2V ferritic steel with the cost-effectiveness, in which concentration limits of activation elements in F82H were relaxed because of the less number of neutron generations from deuterium operations on JT-60U. The fabricated ferritic steel has clear tempered martensitic microstructure, and sufficient magnetic and mechanical properties. The saturated magnetization was estimated to 1.7 Tesla at 573 K, lower than expected, but effectiveness in JT-60U was confirmed by numerical analyses. To research the effect of material conditions, such as microstructure and heat treatment, on saturated magnetization of the ferritic steel based on 8-9Cr is important for the future fusion reactors which will be planned to install the ferritic steel as the in-vessel components.
Ando, Toshinari*; Kizu, Kaname; Miura, Yushi*; Tsuchiya, Katsuhiko; Matsukawa, Makoto; Tamai, Hiroshi; Ishida, Shinichi; Koizumi, Norikiyo; Okuno, Kiyoshi
Fusion Engineering and Design, 75-79, p.99 - 103, 2005/11
Times Cited Count:1 Percentile:10.41(Nuclear Science & Technology)no abstracts in English
Urata, Kazuhiro*; Shinohara, Koji; Suzuki, Masanobu*; Kamata, Isao*
JAERI-Data/Code 2004-007, 45 Pages, 2004/03
As the toroidal magnetic field generated by discrete TF coils involves magnetic field ripple, the fast ion loss is induced to damage vacuum vessel in tokamaks. An idea of ripple compensation using ferromagnetic is proposed. Since low activation ferritic steel have low activation and thermal conduction properties, the ferritic steel is planned to install in tokamak reactors. Installation of ferritic steel plates with toroidal symmetry is effective to compensate ripple, however in the actual devices it is difficult for interference with other components. Besides the first wall shapes are often asymmetric. So it is better to treat toroidal asymmetry to evaluate the ripple induced loss in the actual devices. For the purpose, magnetic field calculation code considering ferritic steel; FEMAG(FErrite generating MAGnetic field)has been speeded up. On the basis of this magnetic field data, OFMC (Orbit Following Monte Carlo) has been upgraded to treat toroidal asymmetry. The use of FEMAG/OFMC, applications to the JFT-2M experiments, and the national centralized tokamak facility are reported.
Furukawa, Masaru; Tokuda, Shinji
Journal of Plasma and Fusion Research SERIES, Vol.6, p.210 - 213, 2004/00
A model equation for ballooning modes in toroidally rotating tokamaks is derived. It is confirmed that the model equation is appropriate for analyzing the stabilization mechanism of the ballooning modes by comparing the numerical solutions of the model equation with those of the original ballooning equations.
Ishii, Yasutomo; Azumi, Masafumi; Kishimoto, Yasuaki
Physics of Plasmas, 10(9), p.3512 - 3520, 2003/09
Times Cited Count:12 Percentile:36.95(Physics, Fluids & Plasmas)no abstracts in English
Hamada, Kazuya; Koizumi, Norikiyo
Purazuma, Kaku Yugo Gakkai-Shi, 78(7), p.616 - 624, 2002/07
In the Tokamak type fusion reactor design, a forced flow superconducting coil is applied from the viewpoint to high magnetic field, high withstand voltage performance and large electromagnetic force. In the forced flow magnets, it is well known that various electromagnetic phenomena are occurred by zero resistance and diamagnetic effect of superconductor and complicated structure of cable in conduit conductor (CICC). In the R&D of CICC, the study of hysteresis losses and coupling losses CICC have a lot of progress. For example, using the optimization of filament arrangement in superconducting strand and control of contact resistance of strand, ITER model coil project have a large achievement.
W.Liu*; Miura, Yukitoshi; JFT-2M Group
Purazuma, Kaku Yugo Gakkai-Shi, 74(7), p.753 - 757, 1998/07
no abstracts in English
J.R.Miller*; L.Bottura*; Koizumi, Koichi; A.Kostenko*; J.Minervini*; N.Mitchell*; Tada, Eisuke; Yoshida, Kiyoshi
IAEA-CN-53/F-3-7, 7 Pages, 1990/00
no abstracts in English
; ; ;
JAERI-M 85-189, 11 Pages, 1985/11
no abstracts in English
; ; ; ; ;
Teion Kogaku, 19(2), p.163 - 169, 1984/00
no abstracts in English
; ; Hiyama, Tadao; ; ; ; ; ; ; ; et al.
JAERI-M 82-044, 189 Pages, 1982/06
no abstracts in English
Yoshida, H.; ; ; Sengoku, Seio; ; ; ;
JAERI-M 9789, 28 Pages, 1981/11
no abstracts in English
; ; Hiyama, Tadao; ; ; ; ; ; ; ; et al.
IEEE Transactions on Magnetics, 17(5), p.1734 - 1737, 1981/00
no abstracts in English
; ; Hiyama, Tadao; ; ; ; ; ; ; ; et al.
IEEE Transactions on Magnetics, 17(5), p.2234 - 2237, 1981/00
Times Cited Count:1 Percentile:29.82(Engineering, Electrical & Electronic)no abstracts in English
; *;
Journal of the Physical Society of Japan, 50(2), p.655 - 658, 1981/00
Times Cited Count:6 Percentile:53.82(Physics, Multidisciplinary)no abstracts in English
JAERI-M 8666, 230 Pages, 1980/03
no abstracts in English
Matsuoka, Seikichi*; Idomura, Yasuhiro; Satake, Shinsuke*
no journal, ,
When non-axisymmetric magnetic perturbations are imposed in axisymmetric tokamaks, broken axisymmetry induces the neoclassical viscosity, and affects momentum transport and resulting plasma rotation profiles. In this work, we estimate the neoclassical toroidal viscosity using full-f gyrokinetic simulations, and verify calculation methods and obtained results. We discuss the parameter dependency of the neoclassical toroidal viscosity in the presence of small resonant magnetic perturbations, based on comparisons against analytic theories and neoclassical transport codes.