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200 BURRELL et al. mode is more stable at higher current [12]. At 1.7 MA/s, the time between ELMs initially lengthened, but the plasma then entered a 100 ms to 150 ms long L—phase. This phase ended when the current ramp ceased. This L-phase began with an ELM that looked very similar to the others prior to it; however, at this high a current ramp rate, the plasma was apparently unable to return to the H-phase. This indicates that the L to H transition is inhibited by current ramping. Similar transient loss of H—mode during current ramps has been seen on ASDEX [20]. In no case did we see an increase in ELM frequency, which would have indicated that the ELM was driven more unstable by an increasing current gradient. Accordingly, ELMs do not appear to be current driven modes. 4. ENERGY CONFINEMENT TIME SCALING IN H-MODE We have investigated energy confinement time scaling as a function of plasma ion species (H, D, He); PT; nc; Ip and BT in discharges with NBI [19]. Energy confinement scaling work as been done in three types of hydrogen plasma with different isotope mixtures: (1) essentially pure deuterium (fractional edge hydrogen concentration [H]/[H+D] < 10%), (2) mixed H/D plasmas ([H]/[H+D] = 30% to 50%) and (3) pure hydrogen plasmas. The admixture of hydrogen in the deuterium plasmas is the result of hydrogen NBI. Confinement is best in deuterium plasmas [2]; TE in pure hydrogen plasmas is about a factor of two smaller; TE in the mixed plasmas lies between the two extremes [19]. In helium plasmas with helium NBI; the confinement results are very similar to those in pure hydrogen plasmas [19]. In deuterium plasmas, we have determined that H-mode 7^ is independent of ne and PT over the range 2.9 < ne (10 19 rn~ 3 ) < 5.5 and 0.8 < PT (MW) < 6.4 [2]. Mixed H/D plasmas and pure hydrogen plasmas show a decrease of T^ with increasing input power [19]. The reason for the difference between hydrogen and deuterium is not yet understood. In mixed H/D H—mode plasmas, we have demonstrated that TQ scales linearly with Ip up to the 2.0 MA level at BT — 2.1 T. This is illustrated in Fig. 5. These data all have qa5 > 3.2. However, as is also shown in Fig. 5, when q95 is lowered by lowering BT to 1.5 T, the increase of confinement with Ip appears to saturate at q95 = 3. This saturation has also been confirmed by ramping the current during H-mode from 1.4 MA to 1.6 MA at 1.5 T while maintaining constant NBI input power; no change in stored plasma energy was seen. Finally, by varying the toroidal field, we have found that TE is proportional to BT at fixed qgs < 3. This lack of Ip scaling at qg5 < 3 has been seen previously at BT < 0-9 T in the high /3r portion of our work [18,19]. Since this loss of Ip scaling occurs for qg5 < 3 at a variety of /3r values, we can conclude that it is not caused by approaching a /?T limit. We have also considered the hypothesis that this loss of Ip scaling might be due to reaching the saturated Ohmic confinement level described by Shimomura, etal. [21].
E m F LU LJU Z o N_ CE UU o / UJ q o CM 50.0 100.0 0.0 m 0.0 IAEA-CN-50/A-III-4 201 BT = 1.5 T PB = 6.7 • q95 i 2.8 O Q95 S 3 o/'er PB ,y° BT = 2.1 T = 8.5 MW /^ O
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The cover picture shows the inside
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AFGHANISTAN ALBANIA ALGERIA ARGENTI
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PLASMA PHYSICS AND CONTROLLED NUCLE
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EDITORIAL NOTE The Proceedings have
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A. Kaminaga, T. Kaneko, T. Kato, M.
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Improved confinement regimes with O
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Tokamak with strong magnetic field
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Resonant island divertor experiment
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Particle removal capabilities of th
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Inside launch electron cyclotron he
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T. Hjima, S. Ishida, K. Itami, T. I
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T. Yamauchi, I. Nakazawa, K. Hasega
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ARTSIMOVICH MEMORIAL LECTURE C. MAI
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IAEA-CN-50/A-0 5 ceptible to fast r
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IAEA-CN-50/A-0 7 fusion power plant
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FIRST EXPERIMENTS IN TORE SUPRA EQU
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IAEA-CN-50/A-I-1 11 Supra is the fi
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IAEA-CN-50/A-I-1 13 poloidal field
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nee id interfere >res an j-> 1 O E
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i I •O OJ) — '5 c IS 2 HI 1ZI _
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5.' ' *[Wbl t. 3. 2. 1. _ _ X IAEA-
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nl 30 .29 .28 .27 26 .25 .24 .23 22
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IAEA-CN-50/A-I-1 However, reasonabl
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IAEA-CN-50/A-I-1 25 will make it po
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IAEA-CN-50/A-I-2 AN OVERVIEW OF TFT
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IAEA-CN-50/A-I-2 29 inner belt limi
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IAEA-CN-50/A-I-2 31 0 10 20 TOTAL P
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5 DC LU LU 3 - 1 - Q Q A 1 A IAEA-C
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IAEA-CN-50/A-I-2 35 The question ar
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0.20 0.15 0.10 Rp= 2.45 m a = 0.79
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: . • • 1 IAEA-CN-50/A-I-2 39 1
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LATEST JET RESULTS AND FUTURE PROSP
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Parameter Plasma major radius (Ro)
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1500 IAEA-CN-50/A-I-3 45 2 4 I, (MA
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IAEA-CN-50/A-I-3 47 3.0 3.5 Major r
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I 15 10 5 0 IAEA-CN-50/A-I-3 49 V \
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IAEA-CN-50/A-I-3 51 Magnetic measur
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0.8 0.6 IAEA-CN-50/A-I-3 53 -0.2 12
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10 0.5 Pulse No: 15376 n(He')/ne=1.
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IAEA-CN-50/A-I-3 57 5 10 15 [Pt-dW/
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10 E X 4 H-mode y 0.2 0.4 0.6 0.8 1
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IAEA-CN-50/A-I-3 61 where V is the
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IAEA-CN-50/A-I-3 63 confinement deg
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IAEA-CN-50/A-I-3 65 References [1 ]
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68 JT-60 TEAM T. TANAKA, Y. TANAKA,
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Ip = 3.2 MA lp = 2.7 MA JT-60TEAM R
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72 JT-60TEAM E5695 0 1 2 3 4 5 6 7
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74 JT-60TEAM 3 : LIH *3.1HA 2.8HA A
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76 JT-60TEAM 4.5 5.0 5.5 6.0 6.5 7.
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78 JT-60TEAM 250 "(a) 200 150 50 n
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80 JT-60 TEAM The further developme
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STABILITY OF HIGH BETA DISCHARGES I
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IAEA-CN-50/A-II-l 85 a typical plas
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0.5- 0- 0.8- 0.4- 0.0- IAEA-CN-50/A
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IAEA-CN-50/A-IM 89 absence of the l
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s.o • .5 (a) IAEA-CN-50/A-II-l 91
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IAEA-CN-50/A-II-l 93 stability limi
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IAEA-CN-50/A-II-l 95 [6] STAMBAUGH,
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98 OKABAYASHI et al. PBX-M maximall
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100 1 .0 .6 .0 -.2 -.4 -.6 1.11 CO
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102 0.5 OKABAYASHI et al. Indentati
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104 OKABAYASHI et al. 40 30 I I I I
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106 OKABAYASHI et al. §1 •a J i
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108 OKABAYASHI et al. -2 1 • •
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MHD ACTIVITIES AND RELATED IMPURITY
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0.5 IAEA-CN-50/A-H-3 113 FIG. 1. St
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0) a. II E IAEA-CN-50/A-H-3 115 1 1
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IAEA-CN-50/A-II-3 117 These observa
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6. CONCLUSIONS IAEA-CN-50/A-II-3 11
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122 GAO et al. With hydrogen plasma
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124 GAO et al. P—3.0 r—8.5 SHOT
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126 GAO et al. a) M >
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128 GAO et al. 0.6 0.3 0.0 50 100 r
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SUPERLOW DENSITY EXPERIMENT ON HT-6
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IAEA-CN-50/A-n-S-l 133 (b) Hard X-r
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IAEA-CN-SO/A-n-5-l 135 0 0.2 0.4 0:
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IAEA-CN-50/A-D-5-2 INVESTIGATION OF
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0.14 0.10 0.09 0.08 0.05 0.04 0.03
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TABLE I. REDUCTION OF Xe (m 2 -s')
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IAEA-CN-50/A-II-5-2 143 (3) The lin
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146 FUSSMANN et al. Abstract IMPROV
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148 FUSSMANN et al. 150- 100- 50- 0
Page 176 and 177: 150 FUSSMANN et al. UJ 100- 50- + 2
Page 178 and 179: 152 FUSSMANN et al. In both regimes
Page 180 and 181: 154 FUSSMANN et al. reduced. With c
Page 182 and 183: 156 FUSSMANN et al. and consequentl
Page 185 and 186: THE JET H-MODE AT HIGH CURRENT AND
Page 187 and 188: IAEA-CN-50/A-IH-2 achieve an H-mode
Page 189 and 190: 6.0 40 2.0 (a) 0l=. 5.0 (c) 0 Pulse
Page 191 and 192: IAEA-CN-50/A-III-2 165 reduced in t
Page 193 and 194: IAEA-CN-50/A-HI-2 167 near the firs
Page 195 and 196: IAEA-CN-50/A-III-2 169 plasmas with
Page 197 and 198: I 3s H-mode 8
Page 199 and 200: IAEA-CN-50/A-HI-2 173 The steep tem
Page 201 and 202: IAEA-CN-50/A-III-2 175 available),
Page 203 and 204: IAEA-CN-50/A-III-2 177 (xi0 19 m 3
Page 205 and 206: IAEA-CN-50/A-III-2 179 APPENDIX I T
Page 207: IAEA-CN-50/A-IH-2 181 [16] Bishop,
Page 210 and 211: 184 ZARNSTORFT et al. Abstract TRAN
Page 212 and 213: 186 ZARNSTORFF et al. X-ray spectro
Page 214 and 215: 188 ZARNSTORFF et al. 8 CM e CM E 2
Page 216 and 217: 190 ZARNSTORFF et al. 1.5 2.0 2.5 n
Page 219 and 220: IAEA-CN-50/A-III-4 ENERGY CONFINEME
Page 221 and 222: o O •
Page 223 and 224: 0.3 0.2- 0.1- 0.0 0.8 0.6 0.4 0.2 0
Page 225: 00 d f CM I- CQ i o o o IAEA-CN-50/
Page 229 and 230: IAEA-CN-50/A-m-4 203 The TB values
Page 231: IAEA-CN-50/A-HM 205 [7] OHYABU, N.,
Page 234 and 235: 208 SUZUKI et al. favourable in a c
Page 236 and 237: 210 SUZUKI etal. As the neutral bea
Page 238 and 239: 212 SUZUKI et al. 3. FOUR-PELLET IN
Page 241 and 242: HEATING OF PEAKED DENSITY PROFILES
Page 243 and 244: Yd o g a> - c 4 _n ...— 0) n 12 t
Page 245 and 246: 1.3 I" 1 |03 C 0.5 i: 12 8 4 n - Te
Page 247 and 248: IAEA-CN-50/A-IV-l 221 1 2 3 Q,_-2ff
Page 249 and 250: 2 q(o) 1- 10 1 U • O • IAEA-CN-
Page 251 and 252: 0.3 f0.2 1 5" 0.1 IAEA-CN-50/A-IV-l
Page 253 and 254: IAEA-CN-50/A-IV-l 227 APPENDIX I TH
Page 255 and 256: IAEA-CN-50/A-IV-2 PELLET INJECTION
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Page 259 and 260: 0 FIG. 4. ONI O £ at o ID c IC 15
Page 261 and 262: IAEA-CN-50/A-IV-2 0.35 MW 2.6 MW Ga
Page 263: IAEA-CN-50/A-IV-2 237 finement. The
Page 266 and 267: 240 AZIZOV et al. TABLE I. TSP PARA
Page 268 and 269: 242 AZIZOV et al. 65 75 85 95 105 1
Page 270 and 271: 244 AZIZOV et al. 30 40 50 60 Ip =
Page 273 and 274: HIGH TEMPERATURE EXPERIMENTS AND FU
Page 275 and 276: IAEA-CN-50/A-IV-4 249 FIG. 1. Data
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P ICRHV 2 IAEA-CN-50/A-IV-4 251 FIG
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IAEA-CN-SO/AIV-4 253 FIG. 4. (a) Di
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IAEA-CN-50/A-IV-4 255 The fusion pe
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258 STRACHAN et al. - Z - 1, Steady
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260 STRACHAN et al. 10' 10' Classic
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262 STRACHAN et al. _ 1 s 10* I : 1
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ENERGY CONFINEMENT WITH AUXILIARY H
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E6950(Bi=4.0T) E6956(Bt = 2.7T) °4
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E7558 • IMPROVED 5 6 TIME (S) IAE
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7.0 E - 1 0.0 7.0 0.0 =— \ n; - T
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IAEA-CN-50/A-V-1 273 [9] SHIMOMURA,
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276 ASHRAF et al. However, the conv
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278
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280 ASHRAF et al. Modulation amplit
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282 KIMet al. (a) (b) 410 420 TIME
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284 KIM et al. (b) o 3
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286 KIM et ah In summary, we observ
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288 KAWAHATA et al. TEXT tokamak, t
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290 KAWAHATA et al. ^ 30 °- S-200.
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292 KAWAHATA et al. 0 6 12 18 24 ra
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294 WOOTTON et al. 1. Particle tran
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296 10' N 10° E gio- 1 O (a) 10" 0
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298 WOOTTON et al. ne=3xl0 19 m- 3
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300 ZURRO et al. FIG. 1. Variation
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302 ZURRO et al. Mo) 6 (10"cm- 3 )
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304 ZURRO et al. -140 50 100 f(kHz)
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TRANSPORT STUDIES ON TFTR UTILIZING
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IAEA-CN-50/A-V-4 309 uses the TRANS
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5 g 30 20 < 2.0 Q § 1.0 i 0.5 10 1
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IAEA-CN-50/A-V-4 313 the laser-blow
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IAEA-CN-S0/A-V-4 315 on working gas
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I0 7 ! 10' 1.8 IAEA-CN-50/A-V-4 317
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IAEA-CN-50/A-V-4 319 The difference
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IAEA-CN-50/A-V-4 321 [12] RADEZTSKY
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324 DONNE et al. E CO o FIG. 1. Sho
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326 DONNE et al. 350 300 250 200 15
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328 DONNE et al. 1.0 0.8 - 0.6 - t
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RECENT TEXTOR RESULTS TEXTOR TEAM (
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IAEA-CN-50/A-VI-l 333 line-radiatio
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IAEA-CN-50/A-VI-l 335 These measure
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q(r] 3- 2- 1- - IAEA-CN-50/A-VI-l 3
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IAEA-CN-50/A-VI-l 339 FIG. 4. Sawto
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IAEA-CN-S0/A-VI-2-1 RESONANT ISLAND
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IAEA-CN-50/A-VI-2-1 343 • «• >
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IAEA-CN-50/A-VI-2-1 345 tons. This
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348 EVANS et al. JIPP T-IIU ( minor
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350 EVANS et al. FIG. 3. High speed
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352 EVANS et al. REFERENCES [1] KAR
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354 BAKOS et al. The radiation of t
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356 BAKOS et al. < + s 5 2 1 5 2 10
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358 BAKOS et al. REFERENCES [1] BAK
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360 STfiCKEL et al. A quantitative
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362 STOCKEL et al. This and other f
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364 STOCKEL et al. 15 I 10 "" 5 0 (
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GLOBAL POWER BALANCE AND LOCAL HEAT
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0.5 1 r. (s> Goldston IAEA-CN-50/A-
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IAEA-CN-50/A-VH-l 371 Separate Elec
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IAEA-CN-50/A-VII-l 373 4. SIMULATIO
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6. CONCLUSIONS IAEA-CN-50/A-VII-l 3
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SAWTOOTH ACTIVITY AND CURRENT DENSI
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-0.6 (keV) 6.6 6.4 6.2 6.0 5.8 IAEA
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IAEA-CN-50/A-VII-2 381 #15697 . 0 1
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IAEA-CN-50/A-VII-2 383 radius. In a
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IAEA-CN-50/A-VH-2 385 [11] Goldston
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388 NAGAYAMA et al. of the magnetic
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390 NAGAYAMA et al. RECONNECTION RE
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392 NAGAYAMA et al. m/n=2/1 island
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STABILITY OF TFTR PLASMAS IAEA-CN-5
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IAEA-CN-50/A-VII-4 397 the electron
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9 8 — 7 6 5 4 - 3 2 X • * • i
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0.5 ' 0.4 0.3 - 3 0.2 0.1 - 0 —r"
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0.4 0.3 0.2 0.1 n IAEA-CN-50/A-VH-4
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Ip(MA) 0.85 0.89 0.9 0.9 1.4 IAEA-C
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IAEA-CN-50/A-VH-4 407 ACKNOWLEDGMEN
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410 AGIM et al. , , , , I , , , .,
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412 AGIM et al. to diminish and the
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414 AGIM et al. Hence, the preventi
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416 MAUELetal. Small tokamak plasma
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418 MAUELetal. 3. Mode structure of
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420 100- 350 MAUEL et al. RAOIUS (c
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STUDY OF PLASMA MHD STABILITY IN T-
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1.5 _ 1.0 >
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20 £ 15 - " 10 II 5 5 — ECH IAEA
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200 - IAEA-CN-S0/A-Vn-7 429 I I I I
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60 40 20 n / l IAEA-CN-S0/A-VII-7 4
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LU 30 - 20 - 10 - IAEA-CN-50/A-V1I-
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as if 200 - 100 -- 20 - I 10 - 15
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RELAXATION OF q PROFILE IN A HIGH B
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0 0.5 1.0 IAEA-CN-50/A-VII-8 439 .
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0 6 12 (Wall) r(cm) IAEA-CN-50/A-VH
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5. CONCLUSIONS IAEA-CN-50/A-VH-8 44
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446 HENDERetal. An alternative meth
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448 HENDER et al. and Jdriven(max)
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450 HENDER et al. TJ :? Island V 6
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IAEA-CN-50/A-VII-10 PARTICLE REMOVA
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IAEA-CN-50/A-VH-10 455 3. POLOIDAL
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X > o S 6 U- 2- 0 160 • 80 0 1 0.
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IAEA-CN-S0/A-VH-10 459 between scoo
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THE ROLE OF LIMITERS AND WALLS IN I
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Shine through IAEA-CN-50/A-VH-ll 46
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3 01 £ "c t=! o E c 12 10 8 6 4 2
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THE PLASMA BOUNDARY IN JET IAEA-CN-
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o x CO o 3.0 2.0 .2-0.5 'in c 0.3 1
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1 10" IAEA-CN-50/A-VI1-12 LCFS LCFS
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o •£ 0.15 'o = 0.05 C O J3 o 0.0
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IAEA-CN-50/A-VIM2 475 densities, bu
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478 LEONOV et al. 2. INSTALLATION A
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480 LEONOV et al. &r (cm) 0.2 -0.2
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482 LEONOV et al. Uo, at constant p
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484 CHEETHAM et al. We present simu
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486 CHEETHAM et al. 0 20 40 60 30 1
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488 CHEETHAM et al. o LU 3.0 2.8
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490 CHEETHAM et al. sior CO 111 c o
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492 CHEETHAM et al. reported from o
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IAEA-CN-S0/A-Vn-15 EXPERIMENTAL RES
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IAEA-CN-50/A-VII-15 497 800 (a) _ -
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IAEA-CN-50/A-VII-15 499 formation.
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300 4X10' 3 - IAEA-CN-50/A-VII-15 5
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CONCLUSION IAEA-CN-50/A-VU-1S 503 W
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506 KIKUCH1 et al. 1. INTRODUCTION
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508 KIKUCHI et al. 1.0 o.s 1 — -
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510 KIKUCHIetal. REFERENCES [1] ZAR
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STUDY OF DENSITY LIMIT AND LOW q(aL
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IAEA-CN-50/E-I-l-l 515 1 2 3 4 5 ne
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/ / IAEA-CN-50/E-I-l-l 517 / / / /
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(J n 3 o ? 2 i o ' 1 IAEA-CN-50/E-M
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0.03 - 0.02 - 0.01 - IAEA-CN-50/E-I
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CO u CO "o IC 7 - 6 — 5 - 4 - 3 1
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IAEA-CN-50/E-I-l-l REFERENCES 52 5
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528 PRATER et al. 1. INTRODUCTION E
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530 PRATER et al. 0.8 0.6 0.4 0.2 n
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532 PRATER et al. 1.5 x 10 19 m~ 3
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534 PRATER et al. 10 1 0.75 0.25 0.
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536 PRATER et al. added to 1.25 MW
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538 PRATER et al. 2.0 1.5 1.0 0.5 /
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INSIDE LAUNCH ELECTRON CYCLOTRON HE
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0-20 0-15 a CO. 0-10 0-05 0-0 5S g.
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IAEA-CN-50/E-I-3 545 0.25 • (a) 1
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IAEA-CN-50/E-I-3 547 A/3 deduced fr
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IAEA-CN-50/E-I-3 549 ECRH phases as
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552 MOTOJIMA et al. ICRF and plasma
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554 MOTOJIMA et al. (a) 0.6SneS0.9x
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556 MOTOJIMA et al. 0 20 W 60 80 10
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558 5 4 3 2 1 0 60 40 20 0 la) cuto
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560 MOTOJIMA et al. 3 0.005 0 0.2 0
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RF CURRENT DRIVE AND MHD INSTABILIT
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IAEA-CN-50/E-I-5 565 80 PEC
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of x o o i L_ t IAEA-CN-50/E-I-5 56
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IAEA-CN-50/E-I-5 569 FIG. 5. Contou
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HEATING AND CONFINEMENT STUDIES WIT
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R 6 IAEA-CN-50/E-IM 0.5 10 1.5 Ne(r
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IAEA-CN-50/E-II-l FIG. 3. Total rad
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IAEA-CN-50/E-II-l 577 1.0 2.0 Time
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IAEA-CN-50/E-II-l 579 TABLE I. SUMM
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6. SAWTOOTH BEHAVIOUR IAEA-CN-50/E-
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IAEA-CN-50/E-II-2 LONG PULSE HIGH P
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IAEA-CN-50/E-II-2 585 23996 2 3 0 U
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IAEA-CN-50/E-II-2 587 TABLE I. a) C
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t a ce> 03 E cs o. otal 100 90 80 7
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IAEA-CN-50/E-H-2 591 and confinemen
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IAEA-CN-50/E-n-3 EXPERIMENTAL AND T
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§ 1PUTUDE ( $ #•14613 200 (a) 18
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IAEA-CN-50/E-II-3 597 The results o
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to V. (a)' • \ \ \ \ \ \ w \'\ \\
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IAEA-CN-50/E-II-3 601 cccurs progre
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IAEA-CN-50/E-II-3 603 [5] CAMPBELL,
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606 FUJII et al. 1. INTRODUCTION Se
Page 634 and 635:
608 140 " (0,0) PIC= l~ 3 MW 120 '
Page 636 and 637:
610 FUJII et al. ACKNOWLEDGEMENTS T
Page 638 and 639:
612 BATCHELOR et al. resolves this
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614 BATCHELOR et al. •J5 1
Page 642 and 643:
616 BATCHELOR et al. to match asymp
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618 BATCHELOR et al. of T, R, and C
Page 646 and 647:
620 BATCHELOR et al. [3] SMITHE, D.
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622 USHIGUSA et al. 1. INTRODUCTION
Page 650 and 651:
624 USHIGUSA et al. at f = 1.74 GHz
Page 652 and 653:
626 USHIGUSA et al. BT (T) (ms) ao
Page 654 and 655:
628 USHIGUSA et al. [2] JT-60 TEAM,
Page 656 and 657:
630 ITOH et al. , Breakdown 20 40 6
Page 658 and 659:
632 ITOH et al. 1.0 20 30 40 50 60
Page 660 and 661:
634 ITOH et al. 30 |20 a "" 10 n H=
Page 662 and 663:
636 ITOH et al. REFERENCES [1] ITOH
Page 664 and 665:
638 ALLADIO et al. generation of hi
Page 666 and 667:
640 ALLADIO et al. 4 T (keV) 3 2 -
Page 668 and 669:
642 ALLADIO et al. 3 ID 10 2 10' 10
Page 671 and 672:
IAEA-CN-50/E-ID-4 LOWER HYBRID WAVE
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1000 - 500 1001— o — 2 35 IAEA-
Page 675 and 676:
10 10* 10 10 IAEA-CN-50/E-HI-4 649
Page 677 and 678:
IAEA-CN-50/E-III-4 651 density of t
Page 679 and 680:
IAEA-CN-50/E-IU-4 653 I I I I I I F
Page 681 and 682:
CURRENT DRIVE AND CONFINEMENT OF AN
Page 683 and 684:
1.0 -0.5 o - - 4.0 IAEA-CN-50/E-III
Page 685 and 686:
IAEA-CN-50/E-III-5 659 TABLE I. SUM
Page 687 and 688:
IAEA-CN-SO/E-in-S 661 0.4 RADIUS (m
Page 689 and 690:
10' Convection Dominates IAEA-CN-50
Page 691 and 692:
IAEA-CN-50/E-III-5 665 versus unbal
Page 693:
IAEA-CN-50/E-III-5 667 [11] ZARNSTO
Page 696 and 697:
670 SIMONEN et al. Neutral beam cur
Page 698 and 699:
672 SIMONEN et al. 1.6 2.0 FIG. 3.
Page 700 and 701:
674 SIMONEN et al. MHD modes, obser
Page 702 and 703:
676 SIMONEN et al. toroidal drift o
Page 704 and 705:
678 SIMONEN et al. occurs near the
Page 707 and 708:
NEW CURRENT DRIVE AND CONFINEMENT T
Page 709 and 710:
IAEA-CN-50/E-III-7 683 is typically
Page 711 and 712:
IAEA-CN-S0/E-III-7 685 plasma beta
Page 713 and 714:
IAEA-CN-50/E-III-7 687 The equilibr
Page 715:
IAEA-CN-50/E-III-7 689 [8] McGUIRE,
Page 718 and 719:
692 100 a 10- 0.1 WILSON et al. •
Page 720 and 721:
694 WILSON et al. 3. Plasma Heating
Page 722 and 723:
696 WILSON et al. I 3 i - • / Tim
Page 725 and 726:
INVESTIGATION OF ICRH ON THE TUMAN-
Page 727 and 728:
~x o X •9to 12 1 11 10 180 s - 12
Page 729 and 730:
400 - 300 - 200 - I 100 - 35 / 1 ,
Page 731 and 732:
5 - IAEA-CN-50/E-IV-2 r (cm) FIG. 7
Page 733 and 734:
IAEA-CN-50/E-IV-3 CONVERSION AND CY
Page 735 and 736:
IAEA-CN-50/E-IV-3 709 bution, e(j,
Page 737 and 738:
IAEA-CN-S0/E-IV-3 711 FIG. 3. kxPd
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IAEA-CN-50/E-IV-3 713 3. NON-LOCAL
Page 741 and 742:
x exp | ds" ' u ' x -oosgn u d fiV2
Page 743 and 744:
IAEA-CN-50/E-IV-3 717 x If {sin i [
Page 745:
IAEA-CN-5O/E-IV-3 719 2. A non-loca
Page 748 and 749:
722 MOREAU et al. =t _» Here, K is
Page 750 and 751:
724 MOREAU et al. FIG. 1. Modulus o
Page 752 and 753:
726 MOREAU et al. REFERENCES [1] MA
Page 754 and 755:
728 YASAKA et al. 2. EFFICIENT PLAS
Page 756 and 757:
730 YASAKA et al. '£ 1 0.5 0 4 Pne
Page 758 and 759:
732 YASAKA et al. WT-3 1 2 Q,f C 10
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734 invi p o p p •^ CJ -^ o IO o
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736 YAMAMOTO et al. (A) OJ — o (A
Page 764 and 765:
738 YAMAMOTO et al. of Tsx =1.5 keV
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740 PEREVERZEV current drive produc
Page 768 and 769:
742 PEREVERZEV 300 - - 150 ne (10 1
Page 770 and 771:
744 PEREVERZEV 0.2- -0.2- 0.1X10 19
Page 772 and 773:
746 PEREVERZEV The dependences of l
Page 774 and 775:
748 PORKOLAB et al. ASPECT RATIO FI
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750 PORKOLAB et al. 1.0 _, 0.8 1 0.
Page 778 and 779:
752 PORKOLAB et al. X D E o Q_ 1.8
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754 LUO et al. - o £ 3 §. II Ml "
Page 782 and 783:
756 LUO et al. 20 10 ATe ( 1 m11 1
Page 785 and 786:
IAEA-CN-50/E-IV-10 MICROWAVE HEATIN
Page 787 and 788:
n MCPAT _ Analysis IAEA-CN-50/E-IV-
Page 789 and 790:
IAEA-CN-50/E-IV-10 763 3. QUASI-LIN
Page 791 and 792:
IAEA-CN-50/E-IV-10 765 In the limit
Page 793 and 794:
IAEA-CN-50/E-IV-ll SECOND ELECTRON
Page 795 and 796:
IAEA-CN-50/E-IV-ll 769 FIG. ]. Real
Page 797 and 798:
-0.2 IAEA-CN-50/E-IV-ll 771 FIG. 3.
Page 799:
IAEA-CN-50/E-IV-ll 773 gests that i
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