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328 DONNE et al. 1.0 0.8 - 0.6 - t 0.4 : - 0.2 - 0.0 - - 1 OH + TH OH only N t i l l Co) . m=2 tb) , VMILv^^JW^ , FIG. 5. Effects of turbulent heating on global energy confinement in STOR-1M. (a) Energy confinement lime after the current pulse, (b) m = 2, 3 MHD signals and density fluctuation at the edge. BT = LOT. VTH = 3kV. fluctuations at the edge as shown in Fig. 5b. The m = 2 Mirnov oscillations are almost completely suppressed. The onset of anomalous resistivity and concurrent efficient heating occurs when the additional current exceeds 2 kA. The corresponding critical drift parameter vjcs is approximately 5, which is well below the critical value for the onset of typical electrostatic instabilities (e.g. ion acoustic and electrostatic ion cyclotron modes) because of a small temperature ratio T/T^ = 2 - 3 in STOR- 1M. Yet, high-frequency density fluctuations in the ion acoustic regime with a broad spectrum extending to f = 200 MHz have been detected by Langmuir probes during the current pulse. ST0R-1M is a prototype for a larger STOR-M (R = 46 cm, a = 12 cm, BT = IT, Ip(OH) = 40 kA, = 350 eV, = 2 x 10 19 m-3). Stable ohmic discharges with q(a) < 2 and discharge duration of 0.2 s have been achieved. Turbulent heating experiments and low q tokamak operation with rapid current ramp and clamping are planned. The work at the University of Saskatchewan was sponsored by the Natural Sciences and Engineering Research Council of Canada. The travel of O. Mitarai was supported by the National Fusion Program of Canada. The loan of a 2-mm interferometer from PPL (Princeton) is gratefully acknowledged. The work at Rijnhuizen was performed as part of the research program of the association agreement of Euratom and the "Stichting voor Fundamenteel Onderzoek der Materie" (FOM) with financial support from the "Nederlandse Organisatie voor Wetenschappelijk Onderzoek" (NWO) and Euratom.
IAEA-CN-50/A-V-5 329 REFERENCES [1] Kalfsbeek H.W., Magnetic field profiles during turbulent heating in a toroidal hydrogen plasma, Rijnhuizen Report 78-114 (1978) [2] Ishihara O. and Hirose A., Quasilinear evolution of current-driven ion-acoustic instability in a magnetic field, Phys. Rev. Lett. 5.0 (1983) 1783. [3] Nakamura R., Hiraki N., Nakamura Y. and Itoh S., Relaxation of ion energy spectrum just after turbulent heating pulse in TRIAM-I tokamak, Jpn. J. Appl. Phys. 31 (1982) 1095. [4] De Kluiver H. and Lopes Cardozo N.J., Plasma heating by current-driven turbulence, Comments Plasma Phys. Controll. Fusion ii (1988) 211. [5] De Kluiver H. et al., High-temperature, high-beta plasma heating by weak turbulence in the TORTUR tokamak, Phys. Lett. 94A (1983) 156. [6] Pfeiffer W. and Waltz R.E., Empirical scaling laws for energy confinement in ohmically-heated tokamaks, Nucl. Fusion 19 (1979) 51. [7] De Kluiver H., Barth C.J. and Donn6 A.J.H., Current driven turbulence and microturbulent spectra in the TORTUR tokamak, Plasma Phys. Controll. Fusion 30 (1988) 699. [8] Mitarai O., Wolfe S.W., Hirose A. and Skarsgard H.M., Measurement of the image field in the STOR-1M tokamak, Plasma Phys. Controll. Fusion 27 (1985) 395. Kuwahara H. et al., Study of enhanced confinement and q = 2 disruptive modes with fast rising current in the STOR-1M tokamak, Plasma Physics and Controlled Nuclear Fusion Research (Proc. 11th Int. Conf., Kyoto, 1986) Vol. 1, IAEA, Vienna (1987) p. 413. [9] Hirose A., Kawabe T. and Skarsgard H.M., Anomalously rapid current penetration in a toroidal turbulent heating experiment, Phys. Rev. Lett. 29 (1972) 1087.
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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
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150 FUSSMANN et al. UJ 100- 50- + 2
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152 FUSSMANN et al. In both regimes
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154 FUSSMANN et al. reduced. With c
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156 FUSSMANN et al. and consequentl
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THE JET H-MODE AT HIGH CURRENT AND
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IAEA-CN-50/A-IH-2 achieve an H-mode
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6.0 40 2.0 (a) 0l=. 5.0 (c) 0 Pulse
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IAEA-CN-50/A-III-2 165 reduced in t
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IAEA-CN-50/A-HI-2 167 near the firs
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IAEA-CN-50/A-III-2 169 plasmas with
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I 3s H-mode 8
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IAEA-CN-50/A-HI-2 173 The steep tem
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IAEA-CN-50/A-III-2 175 available),
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IAEA-CN-50/A-III-2 177 (xi0 19 m 3
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IAEA-CN-50/A-III-2 179 APPENDIX I T
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IAEA-CN-50/A-IH-2 181 [16] Bishop,
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184 ZARNSTORFT et al. Abstract TRAN
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186 ZARNSTORFF et al. X-ray spectro
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188 ZARNSTORFF et al. 8 CM e CM E 2
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190 ZARNSTORFF et al. 1.5 2.0 2.5 n
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IAEA-CN-50/A-III-4 ENERGY CONFINEME
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o O •
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0.3 0.2- 0.1- 0.0 0.8 0.6 0.4 0.2 0
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00 d f CM I- CQ i o o o IAEA-CN-50/
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E m F LU LJU Z o N_ CE UU o / UJ q
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IAEA-CN-50/A-m-4 203 The TB values
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IAEA-CN-50/A-HM 205 [7] OHYABU, N.,
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208 SUZUKI et al. favourable in a c
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210 SUZUKI etal. As the neutral bea
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212 SUZUKI et al. 3. FOUR-PELLET IN
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HEATING OF PEAKED DENSITY PROFILES
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Yd o g a> - c 4 _n ...— 0) n 12 t
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1.3 I" 1 |03 C 0.5 i: 12 8 4 n - Te
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IAEA-CN-50/A-IV-l 221 1 2 3 Q,_-2ff
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2 q(o) 1- 10 1 U • O • IAEA-CN-
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0.3 f0.2 1 5" 0.1 IAEA-CN-50/A-IV-l
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IAEA-CN-50/A-IV-l 227 APPENDIX I TH
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IAEA-CN-50/A-IV-2 PELLET INJECTION
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3 - 2 - 1 - IAEA-CN-50/A-IV-2 231 1
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0 FIG. 4. ONI O £ at o ID c IC 15
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IAEA-CN-50/A-IV-2 0.35 MW 2.6 MW Ga
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IAEA-CN-50/A-IV-2 237 finement. The
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240 AZIZOV et al. TABLE I. TSP PARA
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242 AZIZOV et al. 65 75 85 95 105 1
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244 AZIZOV et al. 30 40 50 60 Ip =
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HIGH TEMPERATURE EXPERIMENTS AND FU
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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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Page 314 and 315: 288 KAWAHATA et al. TEXT tokamak, t
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Page 318 and 319: 292 KAWAHATA et al. 0 6 12 18 24 ra
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Page 326 and 327: 300 ZURRO et al. FIG. 1. Variation
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Page 374 and 375: 348 EVANS et al. JIPP T-IIU ( minor
Page 376 and 377: 350 EVANS et al. FIG. 3. High speed
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Page 380 and 381: 354 BAKOS et al. The radiation of t
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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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RF CURRENT DRIVE AND MHD INSTABILIT
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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
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608 140 " (0,0) PIC= l~ 3 MW 120 '
Page 636 and 637:
610 FUJII et al. ACKNOWLEDGEMENTS T
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612 BATCHELOR et al. resolves this
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614 BATCHELOR et al. •J5 1
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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
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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
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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-
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10 10* 10 10 IAEA-CN-50/E-HI-4 649
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IAEA-CN-50/E-III-4 651 density of t
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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
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IAEA-CN-SO/E-in-S 661 0.4 RADIUS (m
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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
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670 SIMONEN et al. Neutral beam cur
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672 SIMONEN et al. 1.6 2.0 FIG. 3.
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674 SIMONEN et al. MHD modes, obser
Page 702 and 703:
676 SIMONEN et al. toroidal drift o
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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. •
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694 WILSON et al. 3. Plasma Heating
Page 722 and 723:
696 WILSON et al. I 3 i - • / Tim
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INVESTIGATION OF ICRH ON THE TUMAN-
Page 727 and 728:
~x o X •9to 12 1 11 10 180 s - 12
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400 - 300 - 200 - I 100 - 35 / 1 ,
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5 - IAEA-CN-50/E-IV-2 r (cm) FIG. 7
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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
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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
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730 YASAKA et al. '£ 1 0.5 0 4 Pne
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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
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738 YAMAMOTO et al. of Tsx =1.5 keV
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740 PEREVERZEV current drive produc
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742 PEREVERZEV 300 - - 150 ne (10 1
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744 PEREVERZEV 0.2- -0.2- 0.1X10 19
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746 PEREVERZEV The dependences of l
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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 "
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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-
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IAEA-CN-50/E-IV-10 763 3. QUASI-LIN
Page 791 and 792:
IAEA-CN-50/E-IV-10 765 In the limit
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IAEA-CN-50/E-IV-ll SECOND ELECTRON
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IAEA-CN-50/E-IV-ll 769 FIG. ]. Real
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-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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