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8 MAISONNIER Some of the ITER Parties also have national plans to embark, at about the same time, on the detailed design of a similar Next Step. I will not attempt to make any prediction on the framework in which the Next Step(s) will eventually be built. What is clear to me is that we will have to work hard, keeping open all options, to prepare the ground for a decision to start the realization of the Next Step(s) early in the 1990s.
FIRST EXPERIMENTS IN TORE SUPRA EQUIPE TORE SUPRA (Presented by R. Aymar) CEA, Centre d'etudes nucleaires de Cadarache, Departement de recherche sur la fusion controlee, Association Euratom-CEA sur la fusion, Saint-Paul-lez-Durance, France Abstract IAEA-CN-50/A-I-1 FIRST EXPERIMENTS IN TORE SUPRA. First plasma experiments in the large superconducting tokamak Tore Supra (R = 2.37 m; a = 0.8 m) are presented. During the first months of operation (April to July 1988) helium plasmas with nc = 2.5 x 10 19 m"\ Ip = 700 kA and BT = 2 T were routinely obtained, the first wall being baked (210°C) and carbonized. 1. INTRODUCTION Tore Supra is a tokamak equipped with superconducting toroidal field coils. Its design parameters are listed in Table I. The project phase started in January 1977, and the decision for construction was taken in October 1981. The first plasma was obtained at the beginning of April 1988. Tore Supra's main objectives are oriented towards both technology and physics issues in hot, dense, quasi-steady-state plasmas. In particular, it is intended (a) to build and to operate a superconducting magnet large enough to be relevant to a tokamak reactor; (b) to integrate a large cryogenic system into the real environment of a tokamak; (c) to inject and to remove, at quasi-steady state, the tens of megawatts needed to heat the plasma; (d) to control the plasma density and plasma-wall interaction by active methods, i.e. pellet injectors, pump Hmiters and ergodic divertors; (e) to drive the plasma current by propagating waves, starting with lower hybrid waves. Besides the superconducting toroidal field coils (Nb-Ti superconductor cooled by pressurized superfluid helium at 1.8 K) [1], another special feature of Tore
Page 2: The cover picture shows the inside
Page 6 and 7: AFGHANISTAN ALBANIA ALGERIA ARGENTI
Page 8 and 9: PLASMA PHYSICS AND CONTROLLED NUCLE
Page 10 and 11: EDITORIAL NOTE The Proceedings have
Page 12 and 13: A. Kaminaga, T. Kaneko, T. Kato, M.
Page 14 and 15: Improved confinement regimes with O
Page 16 and 17: Tokamak with strong magnetic field
Page 18 and 19: Resonant island divertor experiment
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Page 31 and 32: IAEA-CN-50/A-0 5 ceptible to fast r
Page 33: IAEA-CN-50/A-0 7 fusion power plant
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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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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
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608 140 " (0,0) PIC= l~ 3 MW 120 '
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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.
Page 648 and 649:
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
Page 673 and 674:
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
Page 739 and 740:
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
Page 760 and 761:
734 invi p o p p •^ CJ -^ o IO o
Page 762 and 763:
736 YAMAMOTO et al. (A) OJ — o (A
Page 764 and 765:
738 YAMAMOTO et al. of Tsx =1.5 keV
Page 766 and 767:
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
Page 776 and 777:
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
Page 780 and 781:
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
Page 802:
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