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ICRF Heated Long-Pulse Plasma Discharges in LHD 被引量:17
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作者 R. KUmAZAWA T. SEKI +54 位作者 T. mUTOH K. SAITO T. WATARI Y. NAKAmURA m. SAKAmOTO T. WATANABE S. KUBO T. SHImOZUmA Y. YOSHImURA H. IGAmI Y. TAKEIRI Y. OKA K. TSUmORI m. osakabe K. IKEDA K. NAGAOKA O. KANEKO J. mIYAZAWA S. mORITA K. NARIHARA m. SHOJI S. mASUZAKI m. GOTO T. mORISAKI B. J. PETERSON K. SATO T. TOKUZAWA N. ASHIKAWA K. NISHImURA H. FUNABA H. CHIKARAISHI T. NOTAKE Y. TORII H. OKADA m. ICHImURA H. HIGAKI Y. TAKASE H. KASAHARA F. SHImPO G.NOmURA C.TAKAHASHI m.YOKOTA A. KATO 赵燕平 J. S. YOON J. G. KWAK H. YAmADA K. KAWAHATA N. OHYABU K. IDA Y. NAGAYAmA N. NODA A. KOmORI S. SUDO O. mOTOJImA 《Plasma Science and Technology》 SCIE EI CAS CSCD 2006年第1期28-32,共5页
A long-pulse plasma discharge for more than 30 min. was achieved on the Large Helical Device (LHD). A plasma of ne = 0.8 × 10^19 m^-3 and T10 = 2.0 keV was sustained with PICH = 0.52 MW, PECH = 0.1 MW and avera... A long-pulse plasma discharge for more than 30 min. was achieved on the Large Helical Device (LHD). A plasma of ne = 0.8 × 10^19 m^-3 and T10 = 2.0 keV was sustained with PICH = 0.52 MW, PECH = 0.1 MW and averaged PNBI = 0.067 MW. Total injected heating energy was 1.3 G J, which was a quarter of the prepared RF heating energy. One of the keys to the success of the experiment was a dispersion of the local plasma heat load to divertors, accomplished by shifting the magnetic axis inward and outward. 展开更多
关键词 helical/stellarator configuration ICRF heating steady state operation
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Contribution of the Large Helical Device Plasmas to Alfvén Eigenmode Physics in Toroidal Plasmas 被引量:1
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作者 K. TOI m. ISOBE +14 位作者 m. osakabe F. WATANABE K. OGAWA T. TOKUZAWA A. SHImIZU T. IDO K. IDA, T. ITO S. mORITA K. NAGAOKA K. NARIHARA m. NISHIURA S. OHDACHI S. SAKAKIBARA K. TANAKA LHD Experiment Group 《Plasma Science and Technology》 SCIE EI CAS CSCD 2009年第4期377-380,共4页
In the large helical device (LHD) having three dimensional configuration, Alfven eigenmodes (AEs) destabilized by energetic ions are widely investigated using neutral beam heated plasmas with monotonic and non-mon... In the large helical device (LHD) having three dimensional configuration, Alfven eigenmodes (AEs) destabilized by energetic ions are widely investigated using neutral beam heated plasmas with monotonic and non-monotonic rotational transform (l/2π) profiles. In a plasma with monotonic l/2π-profile, core-localized toroidicity-induced Alfven eigenmode (TAE) as well as global one are often observed. With the increase in the averaged toroidal beta value, defined as the ratio of total plasma pressure to toroidal magnetic pressure, core-localized TAE with low toroidal mode number becomes global. In a relatively high beta plasma with monotonic l/2π-profile, two TAEs with different toroidal mode number often interact nonlinearly and generate another modes through three wave coupling. In a plasma with non-monotonic l/2π-profile generated by intense counter neutral beam current drive, reversed shear Alfven eigenmode (RSAE) and geodesic acoustic mode (CAM) excited by energetic ions were observed for the first time in a helical plasma. Nonlinear coupling was also observed between RSAE and GAM. 展开更多
关键词 alpha particles Alfven eigenmodes geodesic acoustic mode helical/stellarator
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Review of Divertor Studies in LHD 被引量:6
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作者 T. mORISAKI S. mASUZAKI +33 位作者 A. KOmORI N. OHYABU m. KOBAYASHI J. mIYAZAWA m. SHOJI 高翔 K. IDA K. IKEDA O. KANEKO K. KAWAHATA S. KUBO S. mORITA K. NAGAOKA H. NAKANISHI K. NARIHARA Y. OKA m. osakabe B. J. PETERSON S. SAKAKIBARA R. SAKAmOTO T. SHImOZUmA Y. TAKEIRI K. TANAKA K. TOI, K. TSUmORI K. Y. WATABABE T. WATARI H. YAmADA I. YAmADA 严龙文 杨青巍 杨愚 Y.YOSHImURA m. YOSHINUmA O. mOTOJImA 《Plasma Science and Technology》 SCIE EI CAS CSCD 2006年第1期14-18,共5页
In the Large Helical Device (LHD), two different divertor configurations, i.e. helical divertor (HD) and local island divertor (LID), are utilized to control the edge plasma. The HD with two X-points is an intri... In the Large Helical Device (LHD), two different divertor configurations, i.e. helical divertor (HD) and local island divertor (LID), are utilized to control the edge plasma. The HD with two X-points is an intrinsic divertor for heliotron devices, accompanied with a relatively thick ergodic layer outside the confinement region. Edge and divertor plasma behavior from low density to high density regimes is presented, referring to the divertor detachment. The effect of the ergodic layer on the edge transport is also discussed. On the other hand, the LID is an advanced divertor concept which realizes a high pumping efficiency by the combination of an externally induced magnetic island and a closed pumping system. Experimental results to confirm the fundamental divertor performance of the LID are presented. 展开更多
关键词 LHD DIVERTOR ergodic layer magnetic island edge plasma
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