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Ide, Shunsuke; JT-60 Team
Plasma Science and Technology, 8(1), p.1 - 4, 2006/01
Times Cited Count:0 Percentile:0.00(Physics, Fluids & Plasmas)Recent progress in development of high performance plasma and efforts to prolong their sustainment towards ITER advanced operations and a steady-state reactor in JT-60U are presented focusing following achievements; N=3 sustained for 6.2s (
4.1tR) without NTMs in normal shear, fBS
0.45 sustained for 5.8s (
2.8tR) under nearly full CD in weak a shear plasma, fBS
0.75 sustained for 7.4s (2.7tR) under nearly full CD in a reversed shear plasma. Furthermore, importance of these results and issues in advanced tokamak development will be discussed.
Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi
Denki Gakkai Rombunshi, A, 125(11), p.943 - 946, 2005/11
Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.
Ide, Shunsuke; JT-60 Team
Nuclear Fusion, 45(10), p.S48 - S62, 2005/10
Times Cited Count:54 Percentile:82.96(Physics, Fluids & Plasmas)no abstracts in English
Kishimoto, Hiroshi; Ishida, Shinichi; Kikuchi, Mitsuru; Ninomiya, Hiromasa
Nuclear Fusion, 45(8), p.986 - 1023, 2005/08
Times Cited Count:42 Percentile:27.12(Physics, Fluids & Plasmas)The Japanese large tokamak JT-60 has been focusing its research emphases to develop a high performance plasma, namely high confinement, high temperature and high density, and to sustain it non-inductively for a long time with possible minimization of external power input. The first demonstration of high bootstrap current discharges in a high-poloidal-beta mode (high-p) and the concept development of a steady-state tokamak reactor SSTR based on this experimental achievement initiated the so-called "advanced tokamak research". The first observation of internal transport barriers in the JT-60 high-
p mode was followed by the world-wide explorations of reversed shear discharges associated with internal transport barriers. The advanced tokamak research is now the major trend of the current tokamak development. A new concept of compact ITER was developed and proposed in the context of this advanced tokamak approach pursued on JT-60.
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.
Miura, Yukitoshi; JT-60 Team
Physics of Plasmas, 10(5), p.1809 - 1815, 2003/05
Times Cited Count:10 Percentile:31.16(Physics, Fluids & Plasmas)no abstracts in English
ITER Physics Expert Group on Disruptions, Plasma Control, and MHD; ITER Physics Expert Group on Energetic Particles, Heating and Current Drive; ITER Physics Expert Group on Diagnostics
Nuclear Fusion, 39(12), p.2577 - 2625, 1999/00
no abstracts in English
Yamagiwa, Mitsuru
Nuclear Science and Engineering, 125(2), p.218 - 222, 1997/00
Times Cited Count:2 Percentile:22.91(Nuclear Science & Technology)no abstracts in English