ICRF Heated Long-Pulse Plasma Discharges in LHD  

作　　者：R. KUMAZAWA T. SEKI 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 

机构地区：[1]National Institute for Fusion Science, Toki, Japan [2]Kyusyu University, Kasuga, Japan [3]Nagoya University, Faculty of Engineering, Nagoya, Japan [4]Kyoto University, Institute of Advanced Energy, Uji, Japan [5]Tsukuba University, Plasma Research Center, Tsukuba, Japan [6]Tokyo University, Graduate School of Frontier Sciences, Tokyo, Japan [7]Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China [8]KAERI, 150 Deogjin-dong, Yuseong-gu, Daejeon, Korea Rep.

出　　处：《Plasma Science and Technology》2006年第1期28-32,共5页等离子体科学和技术（英文版）

基　　金：supported in part by the JSPS-CAS Core-University Program in the field of Plasma and Nuclear Fusion

摘　　要：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.A long-pulse plasma discharge for more than 30 min.was achieved on the LargeHelical Device(LHD).A plasma of n_e=0.8×10^(19)m^(-3)and T_(iO)=2.0 keV was sustained withP_(ICH)=0.52 MW,P_(ECH)=0.1 MW and averaged P_(NBI)=0.067 MW.Total injected heatingenergy was 1.3 GJ,which was a quarter of the prepared RF heating energy.One of the keys to thesuccess of the experiment was a dispersion of the local plasma heat load to divertors,accomplishedby shifting the magnetic axis inward and outward.

关 键 词：helical/stellarator configuration ICRF heating steady state operation 

分 类 号：O532.2[理学—等离子体物理]