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Nakano, Tomohide; Asakura, Nobuyuki; Takenaga, Hidenobu; Kubo, Hirotaka; Miura, Yukitoshi; Shimizu, Katsuhiro; Konoshima, Shigeru; Masaki, Kei; Higashijima, Satoru; JT-60 Team
Nuclear Fusion, 46(5), p.626 - 634, 2006/05
Times Cited Count:21 Percentile:57.18(Physics, Fluids & Plasmas)In order to understand plasma-wall interactions in a long time scale, the discharge pulse length has been extended from 15 s to 65 s, with the NB-heating duration extended to 30 s. Nearly-saturation of the divertor plates was observed in the latter half of long pulse ELMy H-mode discharges. Particle sink into the divertor plates gradually decreased, and subsequently, wall-pumping efficiency became zero. This wall saturation resulted in a rise of the main plasma density without any auxiliary particle supply besides NB with divertor-pumping. Even when the total injected energy reached up to 350 MJ in a discharge, neither sudden increase of carbon generation such as carbon bloom nor increase of the dilution of the main plasma was observed.
Hoshino, Katsumichi; Yamamoto, Takumi; Tamai, Hiroshi; Oasa, Kazumi; Kawashima, Hisato; Miura, Yukitoshi; Ogawa, Toshihide; Shoji, Teruaki*; Shibata, Takatoshi; Kikuchi, Kazuo; et al.
Fusion Science and Technology, 49(2), p.139 - 167, 2006/02
Times Cited Count:2 Percentile:17.14(Nuclear Science & Technology)The main results obtained by the various heating and current drive systems, external coil system and divertor bias system are reviewed from the viewpoint of the advanced active control of the tokamak plasma. Also, the features of each system are described. The contribution of the JFT-2M in these areas are summarized.
Kubo, Hirotaka; JT-60 Team
Plasma Science and Technology, 8(1), p.50 - 54, 2006/01
Times Cited Count:2 Percentile:7.04(Physics, Fluids & Plasmas)no abstracts in English
Shimakura, Noriyuki*; Homma, Mayumi*; Kubo, Hirotaka
Journal of Plasma and Fusion Research SERIES, Vol.7, p.199 - 202, 2006/00
no abstracts in English
Tamai, Hiroshi; Akiba, Masato; Azechi, Hiroshi*; Fujita, Takaaki; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; Hosogane, Nobuyuki; Ichimura, Makoto*; et al.
Nuclear Fusion, 45(12), p.1676 - 1683, 2005/12
Times Cited Count:15 Percentile:45.44(Physics, Fluids & Plasmas)Design studies are shown on the National Centralized Tokamak facility. The machine design is carried out to investigate the capability for the flexibility in aspect ratio and shape controllability for the demonstration of the high-beta steady state operation with nation-wide collaboration, in parallel with ITER towards DEMO. Two designs are proposed and assessed with respect to the physics requirements such as confinement, stability, current drive, divertor, and energetic particle confinement. The operation range in the aspect ratio and the plasma shape is widely enhanced in consistent with the sufficient divertor pumping. Evaluations of the plasma performance towards the determination of machine design are presented.
Takeda, Nobukazu; Kakudate, Satoshi; Nakahira, Masataka
JAERI-Tech 2004-071, 85 Pages, 2005/02
To facilitate easy maintainability, the ITER divertor is divided into 60 cassettes, which are transported for replacement using the remote equipments. The cassette of 25 tons has to be transported and installed with a positioning accuracy less than 2 mm in the limited space under the intense gamma radiation field. Based on these requirements, the following design and tests were performed. (1) Link mechanism was studied to apply to the transportation. A compact mechanism with links is designed through the optimization of the link angle taking account of space requirement and force efficiency. The lifting capacity of 30 tons has been demonstrated. (2) Compact link mechanism was also studied to apply for locking of the cassette. The final positioning accuracy of 0.03 mm for installation from the initial positioning error of 5 mm has been demonstrated. (3) Sensor-based control of the remote equipment was tested using simple sensors. It is found that the positioning accuracy of 0.16 mm has been achieved and this value is sufficient.
Kubo, Hirotaka; Takenaga, Hidenobu; Nakano, Tomohide; Higashijima, Satoru; Shimizu, Katsuhiro; Sawada, Keiji*; Kobayashi, Shinji*; JT-60 Team
Nuclear Fusion Research; Springer Series in Chemical Physics, Vol.78, p.121 - 134, 2004/11
no abstracts in English
Miura, Yukitoshi; Hoshino, Katsumichi; Kusama, Yoshinori
Purazuma, Kaku Yugo Gakkai-Shi, 80(8), p.653 - 661, 2004/08
A series of experimental program on the JAERI Fusion Torus-2M (JFT-2M) was completed in March, 2004. In the experimental operation for 21 years since the first plasma on April 27, 1983, many significant results leading the fusion energy research and plasma physics have been produced in researches on high confinement mode (H-mode), heating and current drive, advanced plasma control, compatibility of low activation ferritic steel with improved confinement mode, etc. Among these results, some important results are presented.
Asakura, Nobuyuki
Purazuma, Kaku Yugo Gakkai-Shi, 80(3), p.190 - 200, 2004/03
Understanding of the divertor and Scrape-off Layer (SOL) plasmas has been progressed during improvements of the compact- and closed-geometry tokamak divertors. Developments of new diagnostics viewing the SOL and upstream of the divertor target (with the finest spatial and/or time resolutions) have contributed to understand the physics mechanisms under large variations of the plasma along and perpendicular to the field lines. Four topics: (i) heat and particle transports upstream of the divertor plate, (ii) burst transport of heat and particles towards the divertor, (iii) SOL plasma flow, and (iv) plasma diffusion in SOL, were reviewed.
JT-60 Team
JAERI-Review 2003-029, 197 Pages, 2003/11
no abstracts in English
Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Cho, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.
Nuclear Fusion, 43(7), p.606 - 613, 2003/07
Times Cited Count:33 Percentile:69.03(Physics, Fluids & Plasmas)no abstracts in English
Takizuka, Tomonori; Arakawa, Kazuya*; Shimizu, Katsuhiro; Hayashi, Nobuhiko; Asakura, Nobuyuki
JAERI-Research 2003-010, 57 Pages, 2003/05
no abstracts in English
Rognlien, T. D.*; Shimada, Michiya
Journal of Nuclear Materials, 313-316, p.1000 - 1004, 2003/03
Times Cited Count:8 Percentile:49.8(Materials Science, Multidisciplinary)Edge Localized Mode (ELM) heat load on material surfaces is a key issue for burning-plasma tokamak experiments, e.g., ITER or FIRE. When a hot and dense plasma is injected to open field lines near the midplane at an ELM event, there will be a pressure imbalance along the field line, because ion motion is slow. Therefore an electric field will develop along the field line(an extended presheath). Due to the rotational transform, the parallel electric field becomes a poloidal electric field. The field Ep generates an . Therefore, as the injected plasma flows toward the divertor surface to deposit its energy, it experiences a radial shift 1cm. As the target plate is usually inclined to reduce the heat load, a radial shift of 1 cm is appreciable. For ITER, this would correspond to 3 cm on the target. As different portions of the hot ion plasma feel different electric field, the heat flux should also spread radially. A detailed assessment of these cross-field drift effects is given for an ITER-sized device using time-dependent simulations with the 2D UEDGE transport code.
Kubo, Hirotaka; Sakurai, Shinji; Higashijima, Satoru; Takenaga, Hidenobu; Itami, Kiyoshi; Konoshima, Shigeru; Nakano, Tomohide; Koide, Yoshihiko; Asakura, Nobuyuki; Shimizu, Katsuhiro; et al.
Journal of Nuclear Materials, 313-316(1-3), p.1197 - 1201, 2003/03
Times Cited Count:20 Percentile:75.71(Materials Science, Multidisciplinary)no abstracts in English
Sugie, Tatsuo; Hatae, Takaki; Koide, Yoshihiko; Fujita, Takaaki; Kusama, Yoshinori; Nishitani, Takeo; Isayama, Akihiko; Sato, Masayasu; Shinohara, Koji; Asakura, Nobuyuki; et al.
Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.482 - 511, 2002/09
Times Cited Count:6 Percentile:3.03(Nuclear Science & Technology)The diagnostic system of JT-60U (JT-60upgrade) is composed of about 50 individual diagnostic devices. Recently, the detailed radial profile measurements of plasma parameters have been improved, so that the internal structure of plasmas has been explored. The understanding of plasma confinement has been enhanced by density and temperature fluctuation measurements using a mm-wave reflectometer and electron cyclotron emission measurements respectively. In addition, the real-time control experiments of electron density, neutron yield, radiated power and electron temperature gradient have been carried out successfully by corresponding diagnostic devices. These measurements and the real time control contribute to improving plasma performance. Diagnostic devices for next generation fusion devices such as a CO2 laser interferometer/polarimeter and a CO2 laser collective Thomson scattering system have been developed.
Nakamura, Yukiharu; Pautasso, G.*; Gruber, O.*; Jardin, S. C.*
Plasma Physics and Controlled Fusion, 44(8), p.1471 - 1481, 2002/08
Times Cited Count:13 Percentile:38.1(Physics, Fluids & Plasmas)no abstracts in English
Kubo, Hirotaka
AIP Conference Proceedings 636, p.161 - 170, 2002/00
no abstracts in English
Hayashi, Nobuhiko; Takizuka, Tomonori; Shimizu, Katsuhiro
Contributions to Plasma Physics, 40(3-4), p.387 - 392, 2000/11
Times Cited Count:2 Percentile:7.86(Physics, Fluids & Plasmas)no abstracts in English
Tsuda, Takashi; Kobayashi, M.*; Kurita, Genichi; Takamura, Shuichi*
Contributions to Plasma Physics, 40(3-4), p.256 - 259, 2000/06
Times Cited Count:4 Percentile:14.83(Physics, Fluids & Plasmas)no abstracts in English
Kumagai, Akira*; Kubo, Hirotaka; Takenaga, Hidenobu; Suzuki, Shingo; Shimizu, Katsuhiro; Asakura, Nobuyuki; Shimada, Michiya
Plasma Physics and Controlled Fusion, 42(5), p.529 - 543, 2000/05
Times Cited Count:13 Percentile:39.64(Physics, Fluids & Plasmas)no abstracts in English