Formation of advanced tokamak plasmas without the use of an ohmic-heating solenoid

被引:48
作者
Shiraiwa, S [1 ]
Ide, S
Itoh, S
Mitarai, O
Naito, O
Ozeki, T
Sakamoto, Y
Suzuki, T
Takase, Y
Tanaka, S
Taniguchi, T
Aramasu, M
Fujita, T
Fukuda, T
Gao, X
Gryaznevich, M
Hanada, K
Jotaki, E
Kamada, Y
Maekawa, T
Miura, Y
Nakamura, K
Nishi, T
Tanaka, H
Ushigusa, K
机构
[1] Univ Tokyo, Grad Sch Frontier Sci, Tokyo 1130033, Japan
[2] Japan Atom Energy Res Inst, Ibaraki 3110193, Japan
[3] Kyushu Univ, Res Inst Appl Mech, Fukuoka 8168580, Japan
[4] Kyushu Tokai Univ, Sch Engn, Kumamoto 8628652, Japan
[5] Kyoto Univ, Dept Phys, Kyoto 6068502, Japan
[6] Univ Tokyo, Grad Sch Sci, Tokyo 1130033, Japan
[7] Osaka Univ, Grad Sch Engn, Osaka 5670047, Japan
[8] Acad Sinica, Inst Plasma Phys, Hefei 230031, Peoples R China
[9] EURATOM, Abingdon OX14 3DB, Oxon, England
[10] Kyoto Univ, Grad Sch Energy Sci, Kyoto 6068502, Japan
关键词
D O I
10.1103/PhysRevLett.92.035001
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
A new operational scenario of advanced tokamak formation was demonstrated in the JT-60U tokamak. This was accomplished by electron cyclotron and lower hybrid waves, neutral beam injection, and the loop voltage supplied by the vertical field and shaping coils. The Ohmic heating (OH) solenoid was not used but a small inboard coil (part of the shaping coil), providing less than 20% of total poloidal flux, was used. The plasma thus obtained had both internal and edge transport barriers, with an energy confinement time of 1.6 times H-mode scaling, a poloidal beta of 3.6, and a normalized beta of 1.6, and a large bootstrap current fraction (>90%). This result opens up a possibility to reduce, and eventually eliminate, the OH solenoid from a tokamak reactor, which will greatly improve its economic competitiveness.
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页数:4
相关论文
共 29 条
[11]   IMPROVED PLASMA PERFORMANCE IN TOKAMAKS WITH NEGATIVE MAGNETIC SHEAR [J].
KESSEL, C ;
MANICKAM, J ;
REWOLDT, G ;
TANG, WM .
PHYSICAL REVIEW LETTERS, 1994, 72 (08) :1212-1215
[12]   TOROIDAL PLASMA CURRENT STARTUP AND SUSTAINMENT BY RF IN THE WT-2 TOKAMAK [J].
KUBO, S ;
NAKAMURA, M ;
CHO, T ;
NAKAO, S ;
SHIMOZUMA, T ;
ANDO, A ;
OGURA, K ;
MAEKAWA, T ;
TERUMICHI, Y ;
TANAKA, S .
PHYSICAL REVIEW LETTERS, 1983, 50 (25) :1994-1997
[13]   Plasma current ramp-up assisted by outer vertical field coils in a high aspect ratio tokamak [J].
Mitarai, O ;
Yoshino, R ;
Ushigusa, K .
NUCLEAR FUSION, 2002, 42 (10) :1257-1272
[14]   Plasma current rampup by the outer vertical field coils in a spherical tokamak reactor [J].
Mitarai, O ;
Takase, Y .
FUSION SCIENCE AND TECHNOLOGY, 2003, 43 (01) :67-90
[15]  
NAJIMABADI F, 1999, FUSION ENERGY 1998
[16]   Overview of the ARIES-RS reversed-shear tokamak power plant study [J].
Najmabadi, F ;
Bathke, CG ;
Billone, MC ;
Blanchard, JP ;
Bromberg, L ;
Chin, E ;
Cole, FR ;
Crowell, JA ;
Ehst, DA ;
El-Guebaly, LA ;
Herring, JS ;
Hua, TQ ;
Jardin, SC ;
Kessel, CE ;
Khater, H ;
Lee, VD ;
Malang, S ;
Mau, TK ;
Miller, RL ;
Mogahed, EA ;
Petrie, TW ;
Reis, EE ;
Schultz, J ;
Sidorov, M ;
Steiner, D ;
Sviatoslavsky, IN ;
Sze, DK ;
Thayer, R ;
Tillack, MS ;
Titus, P ;
Wagner, LM ;
Wang, XR ;
Wong, CPC .
FUSION ENGINEERING AND DESIGN, 1997, 38 (1-2) :3-25
[17]  
NISHIO S, 2002, P 19 IAEA FUS EN C L
[18]  
Nishio S., 2002, J PLASMA FUSION RES, V78, P1218
[19]   TOROIDAL PLASMA CURRENT STARTUP AND SUSTAINMENT BY LOWER HYBRID WAVES IN THE WT-3 TOKAMAK [J].
OGURA, K ;
TANAKA, H ;
IDE, S ;
IIDA, M ;
HANADA, K ;
YOSHIDA, M ;
MINAMI, T ;
NAKAMURA, M ;
MAEKAWA, T ;
TERUMICHI, Y ;
TANAKA, S .
NUCLEAR FUSION, 1990, 30 (04) :611-624
[20]   Compact reversed shear tokamak reactor with a superheated steam cycle [J].
Okano, K ;
Asaoka, Y ;
Yoshida, T ;
Furuya, T ;
Tomabechi, K ;
Ogawa, Y ;
Sekimura, N ;
Hiwatari, R ;
Yamamoto, T ;
Ishikawa, T ;
Fukai, Y ;
Hatayama, A ;
Inoue, N ;
Kohyama, A ;
Shinya, K ;
Murakami, Y ;
Senda, I ;
Yamazaki, S ;
Mori, S ;
Adachi, J ;
Takemoto, M .
NUCLEAR FUSION, 2000, 40 (3Y) :635-646