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Minami, Takashi
Proceedings of the 13th international symposium on laser-aided plasma diagnostics2007
Proceedings of the 13th international symposium on laser-aided plasma diagnostics2007
AbstractAbstract
[en] An in situ density calibration for a Thomson scattering measurement by a microwave reflectometry based on Bayesian estimation is proposed. A simultaneous calibration with a plasma experiment is feasible, because it is not necessary for a vacuum vessel to be filled with N2, Ar or H2 gases. The Bayesian estimation provides an accurate density calibration factor from a few reflectometer measurements, which is confirmed by a Monte-Carlo simulation. (author)
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Kawahata, Kazuo (ed.); National Inst. for Fusion Science, Toki, Gifu (Japan); 295 p; Sep 2007; p. 46-49; 13. International symposium on laser-aided plasma diagnostics; Takayama, Gifu (Japan); 18-21 Sep 2007; 5 refs., 3 figs.
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Minami, Takashi; Okamura, Shoichi; Suzuki, Chihiro
National Inst. for Fusion Science, Toki, Gifu (Japan)2008
National Inst. for Fusion Science, Toki, Gifu (Japan)2008
AbstractAbstract
[en] An edge transport barrier (ETB) formation and an improved L-mode (IL mode) have been simultaneously realized in high density region (n-bare - 1.2x1020m-3) on Compact Helical System (CHS). When the ETB is formed during the IL mode, the density reduction in the edge region is suppressed by the barrier formation. As a result of the continuous increasing of the temperature by the IL mode, the stored energy during the combined mode increased up to the maximum stored energy (Wp - 9.4 kJ) recorded in CHS experiments. The plasma pressure in the peripheral region increases up to three times larger than that of the L-mode, and the large edge plasma pressure gradient is formed accompanying the pedestal structure. That is caused by the anomalous transport reduction that is confirmed from the sharp drop of the density fluctuation in the edge region. The neutral particle reduction in the peripheral region and the metallic impurity accumulation in the core plasma are simultaneously observed during the high density ETB formation. (author)
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Oct 2008; 9 p; 22. IAEA fusion energy conference; Geneva (Switzerland); 13-18 Oct 2008; IAEA-CN--165; EX/P3--11; 18 refs., 5 figs.
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Akiyama, Tsuyoshi; Minami, Takashi, E-mail: takiyama@ms.nifs.ac.jp2006
AbstractAbstract
No abstract available
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28 refs., 5 figs.
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Journal Article
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Purazuma, Kaku Yugo Gakkai-Shi; ISSN 0918-7928; ; v. 82(6); p. 337-341
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[en] An improved confinement mode with reheat and edge transport barrier is observed in the Compact Helical System (CHS). This mode provides enhanced confinement in high density region (n-bare - 1.2 x 1020 m-3) due to the increase in temperature while high density is maintained in the peripheral region. (author)
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Journal Article
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Plasma and Fusion Research; ISSN 1880-6821; ; v. 1; p. 047.1-047.2
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AbstractAbstract
[en] The high ion temperature mode for neutral beam heated plasma is observed in CHS heliotron/torsatron device. Transport analysis for this mode shows that increase in ion temperature is due to improvement of ion heat transport. On the other hand, electron diffusivity in the high ion temperature mode is larger than that in the L-mode. There is a correlation between thermal diffusivity and density gradient. (author)
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Ueda, Y. (Osaka Univ., Suita (Japan)); Iguchi, H.; Matsuoka, K.; Sudo, S. (eds.); 540 p; ISBN 4-9900586-3-3; ; 1998; p. 243-246; ISC-11: 11. international stellarator conference; Toki, Gifu (Japan); 29 Sep - 3 Oct 1997; ITC-8: 8. international Toki conference on plasma physics and controlled nuclear fusion; Toki, Gifu (Japan); 29 Sep - 3 Oct 1997
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[en] A clear transition of edge particle transport was observed for the neutral beam heated plasmas in CHS. The heating power threshold for the transition is about 1 MW for a plasma with 2x1019 m-3 average density. The Hα emission drops within 1 msec and the increase of the local edge density at the transition was confirmed by means of YAG Thomson scattering and beam emission spectroscopy. When the heating power is well above the threshold, the transport barrier is maintained for the full duration of NBI heating (100 msec). A clear back transition appears when the heating power is decreased during the discharge. (author)
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5 refs., 3 figs.
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Journal Article
Journal
Purazuma, Kaku Yugo Gakkai-Shi; ISSN 0918-7928; ; v. 79(10); p. 977-979
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[en] High ion temperature mode (high Ti mode) is observed for neutral beam heated plasmas in Compact Helical System (CHS) Heliotron/torsatron plasmas. The high Ti mode plasma is characterized by a peaked ion temperature profile and is associated with a peaked electron density profile produced by neutral beam fueling. The reduction of ion thermal diffusivity is observed at the plasma core (ρ=0.1) in the high Ti mode by a factor of two. The high Ti mode discharge is observed only in the low density and the upper limit of ne (critical ne) for the high Ti mode depends on the density peaking factor. (author)
Primary Subject
Source
Ueda, Y. (Osaka Univ., Suita (Japan)); Iguchi, H.; Matsuoka, K.; Sudo, S. (eds.); 540 p; ISBN 4-9900586-3-3; ; 1998; p. 239-242; ISC-11: 11. international stellarator conference; Toki, Gifu (Japan); 29 Sep - 3 Oct 1997; ITC-8: 8. international Toki conference on plasma physics and controlled nuclear fusion; Toki, Gifu (Japan); 29 Sep - 3 Oct 1997
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Fujisawa, Akihide; Iguchi, Harukazu; Minami, Takashi
Potential and structure in plasmas: ITC-11 Proceedings2001
Potential and structure in plasmas: ITC-11 Proceedings2001
AbstractAbstract
[en] Bifurcation properties in radial electric field have been studied using a heavy ion beam probe in a toroidal helical plasma of Compact Helical System. This paper presents an overview of the bifurcation phenomena observed in potential structure and its dynamics, such as potential patterns with transport barrier formation, and self-organized oscillation termed electric pulsation. Detailed analysis of this oscillatory state provides an interesting result of spatio-temporal evolutions of potential and density profile during a pulse-like event. (author)
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Tanaka, M.Y.; Fujisawa, A.; Todo, Y.; Matsuoka, K. (National Inst. for Fusion Science, Toki, Gifu (Japan)) (eds.); Inutake, M.; Ando, A. (Tohoku Univ., Graduate School of Engineering, Sendai, Miyagi (Japan)) (eds.); 617 p; ISBN 4-9900586-6-6; ; 2001; p. 54-60; ITC-11: 11. international Toki conference on plasma physics and controlled nuclear fusion; Toki, Gifu (Japan); 5-8 Dec 2000; 26 refs., 5 figs.
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Minami, Takashi; Fujisawa, Akihide; Iguchi, Harukazu
Potential and structure in plasmas: ITC-11 Proceedings2001
Potential and structure in plasmas: ITC-11 Proceedings2001
AbstractAbstract
[en] An improvement of plasma confinement by the addition of electron cyclotron heating (Pinj - 130 kW) to neutral beam injection sustained plasmas has been observed on the CHS heliotron/torsatron device. In the core region inside ρ=0.5, the temperature is increased for both electrons (2300 eV from 300 eV) and ion (400 eV from 200 eV). The change of the electric field structure by transition from ion to electron root is correlated to the improvement of the plasma performance. The condition for this phenomenon occurring depends sensitively on the plasma density. (author)
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Source
Tanaka, M.Y.; Fujisawa, A.; Todo, Y.; Matsuoka, K. (National Inst. for Fusion Science, Toki, Gifu (Japan)) (eds.); Inutake, M.; Ando, A. (Tohoku Univ., Graduate School of Engineering, Sendai, Miyagi (Japan)) (eds.); 617 p; ISBN 4-9900586-6-6; ; 2001; p. 451-456; ITC-11: 11. international Toki conference on plasma physics and controlled nuclear fusion; Toki, Gifu (Japan); 5-8 Dec 2000; 9 refs., 3 figs.
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Yamazaki, Kozo; Minami, Takashi; Narihara, Kazuto; Tanaka, Kenji; Kubo, Shin
Proceedings of joint conference of ITC-12 and APFA'01: Frontiers in plasma confinement and related engineering/plasma science2003
Proceedings of joint conference of ITC-12 and APFA'01: Frontiers in plasma confinement and related engineering/plasma science2003
AbstractAbstract
[en] In the local Electron Cyclotron Heating (ECH) experiments, high electron temperature plasmas have been obtained in Compact Helical System (CHS), and recently in the Large Helical Device (LHD). The internal transport barrier (ITB) with strong positive radial electric field has been experimentally observed in CHS, which reduces neo-classical ripple transport and anomalous transport losses. The same physics pictures are expected in LHD high temperature plasmas. Several ion temperature profiles are assumed for analyzing LHD experimental data, and it is found that the experimentally obtained electron thermal transport coefficients seem to roughly agree with neoclassical ripple transport outside the ITB region. However, around ITB region, about ten times higher than the neoclassical coefficients with strong ambipolar electric field prediction are obtained. The anomalous transport losses might be dominant and be reduced by this strong electric field shear around the ITB region. (author)
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Nishimura, K.; Inagaki, S.; Sanuki, H.; Yamazaki, K. (National Inst. for Fusion Science, Toki, Gifu (Japan)) (eds.); 650 p; ISBN 4-9900586-7-4; ; 2003; p. 611-615; ITC-12: 12. international Toki conference on plasma physics and controlled nuclear fusion; Toki, Gifu (Japan); 11-14 Dec 2001; APFA'01: 3. general scientific assembly of Asia plasma and fusion association; Toki, Gifu (Japan); 11-14 Dec 2001; 5 refs., 3 figs.
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