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Shimada, Michiya; Mukhovatov, V.*; Federici, G.*; Gribov, Y.*; Kukushkin, A.*; Murakami, Yoshiki*; Polevoi, A. R.*; Pustovitov, V. D.*; Sengoku, Seio; Sugihara, Masayoshi
Nuclear Fusion, 44(2), p.350 - 356, 2004/02
Recent performance analysis has improved confidence in achieving Q 
10 in inductive operation in ITER. Performance analysis based on empirical scaling shows the feasibility of achieving Q 10 in inductive operation with a sufficient margin. Theory-based core modeling indicates the need of high pedestal temperature (2-4 keV) to achieve Q 10, which is in the range of projection with pedestal scaling. The heat load of type-I ELM could be made tolerable by high density operation and further tilting the target plate (if necessary). Pellet injection from High-Field Side would be useful in enhancing Q and reducing ELM heat load. Steady state operation scenarios have been developed with modest requirement on confinement improvement and beta (HH98(y,2) 1.3 and betaN 2.6). Stabilisation of RWM, required in such regimes, is feasible with the present saddle coils and power supplies with double-wall structure taken into account.
Shimada, Michiya; Mukhovatov, V.*; Federici, G.*; Gribov, Y.*; Kukushkin, A. S.*; Murakami, Yoshiki*; Polevoi, A. R.*; Pustovitov, V. D.*; Sengoku, Seio; Sugihara, Masayoshi
Nuclear Fusion, 44(2), p.350 - 356, 2004/02
Times Cited Count：39 Percentile：75.67(Physics, Fluids & Plasmas)Performance analysis based on empirical scaling shows the feasibility of achieving Q 
10 in inductive operation. Analysis has also elucidated a possibility that ITER can potentially demonstrate Q 
50, enabling studies of self-heated plasmas. Theory-based core modeling indicates the need of high pedestal temperature (3.2 - 5.3 keV) to achieve Q 10, which is in the range of projection with presently available pedestal scalings. Pellet injection from high-field side would be useful in enhancing Q and reducing ELM heat load in high plasma current operation. If the ELM heat load is not acceptable, it could be made tolerable by further tilting the target plate. Steady state operation scenarios at Q = 5 have been developed with modest requirement on confinement improvement and beta (HH98(y,2) 1.3 and betaN 2.6). Stabilisation of RWM, required in such regimes, is feasible with the present saddle coils and power supplies with double-wall structure taken into account.
Kamada, Yutaka
Purazuma, Kaku Yugo Gakkai-Shi, 79(2), p.123 - 135, 2003/02
This paper reviews recent studies on tokamak MHD stability towards achievement of high beta steady-state, where profile control of current, pressure and rotation, and optimization of the plasma shape play fundamental roles. The key instabilities are the neoclassical tearing mode, the resistive wall mode, the edge localized modes etc. Towards demonstration of an economically attractive tokamak reactor, we need to increase the beta value with sufficiently high integrated plasma performance. Towards this goal, studies on stability control in the self-regulating plasma system are essential.
Iio, Shunji*; Ide, Shunsuke; Ozeki, Takahisa; Sugihara, Masayoshi; Takase, Yuichi*; Takeji, Satoru*; Tobita, Kenji; Fukuyama, Atsushi*; Miyamoto, Kenro*
Purazuma, Kaku Yugo Gakkai-Shi, 78(6), P. 601, 2002/06
no abstracts in English
Takeji, Satoru; Tokuda, Shinji; Kurita, Genichi; Suzuki, Takahiro; Isayama, Akihiko; Takechi, Manabu; Oyama, Naoyuki; Fujita, Takaaki; Ide, Shunsuke; Ishida, Shinichi; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 78(5), p.447 - 454, 2002/05
no abstracts in English
Yoshino, Ryuji; Ozeki, Takahisa; Tokuda, Shinji; Iio, Shunji*; Yamazaki, Kozo*
Purazuma, Kaku Yugo Gakkai-Shi, 76(2), p.116 - 126, 2000/02
no abstracts in English
