FUSION TECHNOLOGY 1998

Proceedings of the 20th Symposium on Fusion TechnologyMarseille, France, 7-11 September 1998

VOLUME 1

20th

SOFT1998

Edited by:

B. BEAUMONT

P. LIBEYRE

B. de GENTILE

G. TONON

Association EURATOM-CEA, Departement de Recherches sur la Fusion Controlee,CEA/CadaracheF-13108 Saint Paul Lez Durance CEDEX (France)

UB/TIB Hannover 891.21.617 580

XIII

TABLE OF CONTENTS

VOLUME 1

Preface VIndustrial exhibitors VIICommittee members VIII

Invited Talks

The European Fusion Programme: Present status and prospectsU.Finzi 3

Status of ITER , July 1998R. Aymar 4

Fusion Physics Progress on JETM. Keilhacker and the JET Team 5

Ten years of operation and developements on Tore SupraJ. Pamela and Tore Supra Team 6

The CERN Large Hadron Collider ProjectLMaiani 7

Socio-economic aspects of fusion : Research in the European contextgenerationL Ingelstam 8

Progress with heating and current drive technologiesD.C. Robinson, M. Cox, B. Lloyd, M. Nightingale 9

RF and microwave tubes for fusionG.Faillon 10

The Ariane ProjectJ.-M. Luton 11

ITER magnets design and R & DN. Mitchell and the ITER Joint Central Team and HomeTeams 12

XIV

Engineering design of the ITER Blanket and relevant R & D resultsF. Elio, K. loki, L Bruno, A. Cardella, Y. Gohar, M. Hechler, T. Kodama,A. Lodato, D. Loesser, D. Lousteau, N. Miki, K. Mohri, R.R. Parker, R. Raff ray,R. T. Santoro, D. Williamson, M. Yamada, W. Daenner, R. Mattas, Y. Strebkov,H. Takatsu 13

Limitations on blanket performancesS. Malang 14

Status of the IFMIF projectT. Shannon, R. Jameson, H. Katsuta, H. Maekawa, M. Martone, A. Moeslang,V. Teplyakov 15

ITER Divertor, issues and R & DR. Tivey, T. Ando, A. Antipenkov, S. Chiocchio, G. Federici, C. Ibbot, R.Jakeman, G. Janeschitz, E. Martin, R. Raffray 16

Safety and environment aspects for a fusion power reactorG. Marbach 17

Tritium inventory issues for future reactors: choices, parameters, limitsD.K. Murdoch, Ch. Day, P. Gierszewski, R.D. Penzhorn, C.H. Wu 18

Laser Mega Joule project and impact of the inertial fusion programmeA. Bettinger, M. Decroisette 19

Design, construction and the first operation of LHDA. liyoshi, S. Imagawa and the LHD Group 20

The technological achievements and experience at JETM.A. Pick and the JET Team 21

Oral Presentations

Active feedback control of steady-state improved confinementdischarges in JT-60UT. Fukuda 25

Operation of the JET active gas handling system during and after DTE1R. Lasser, A.C. Bell, N. Bainbridge, D. Brennan, B. Grieveson,J.L. Hemmerich, G. Jones, D. Kennedy, S. Knipe, J. Lupo, J. Mart,A. Perevesentsev, N. Skinner, R. Stagg, J. Yorkshades, G. V. Atkins, L. Dorr,N. Green, M. Stead, K. Wilson 26

XV

RF sources for fusion applications : design, development andperformanceE. Speth, P. Frank, B. Heinemann, W. Kraus, R. Riedl, R. Trainham,0. Vollmer.R. Wilhelm 27

New developments of the ASDEX Upgrade Tokamak microwavereflectometerA. Silva, L. Cupido, C. Loureiro, S. Vergamota, P. Varela, J. Santos, M. Manso,F. Serra, L. Meneses, M. Tavares, I. Nunes, B. Kurzan, W. Suttrop,V. Grossman 28

Next generation discharge control system for ASDEX upgradeG. Raupp, K. Behler, R. Cole, K. Luddecke, G. Neu, W. Treutterer, V. Mertens,D. Zasche, T. Zehetbauer 29

The ITER toroidal field model coil (TFMC)E. Salpietro, R. Maix, G. Bevilacqua, G. Di Bartolo, H. Fillunger, N. Mitchell,B. Turck, P. Libeyre, A. Ulbricht, M. Spadoni, A. Delia Corte, H. Bieder,D. Bresson, D. Krischel, G.E. Tardivelli 30

ITER reference breeding blanket designM. Ferrari, W. Danner, A. Bianchi, G. Celentano, A. Gerber, W. Gulden, K. loki,S. Khomiakov, T. Kuroda, A. Lopatkin, X. Masson, R. Mattas, G. Mazzone,J. Mustoe, R.R. Parker, L Petrizzi, A. Pizzuto, R. Plenteda, Y. Poitevin,R. Raffray, M. Roccella, Y. Strebkov, H. Takatsu, F. Scaffidi-Argentina,F. Zacchia 31

Objectives Feasibility Assessment of the WCLL Mock-up Testing in ITERL. Giancarli, B. Bielak, M.A. Futterer, O. Ogorodnikova, Y. Poitevin,J.F. Salavy, J. Szczepanski, Y. Severi, G. Marbach, G. Benamati, C. Nardi,J. Reimann 32

European development of the ITER divertor targetG. Vieider, D. Duglue, M. Merola, H.D. Pacher, C.H. Wu, J.P. Bonal,Ph. Chappuis, F. Escourbiac, J. Schlosser, G. Le Marois, R. Duwe, M. Rodig,M. Febvre, M. Grattarola, A. Peacok, A. Pizzuto, B. Riccardi, B. Riccardi,L Plochl, I. Smid, P. Tramier 33

Comparative thermal cyclic testing of different beryllium gradespreviously subjected to plasma disruption scenariosA. Gervash, V. Komarov, I.V. Mazul, N. Jablokov, J. Linke, M. Roedig 34

The Ultimate Safety Margins of ITER: A Demonstration of the SafetyPotential of FusionD.A. Petti, H.W. Bartels 35

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A report on the first remote handling operations at JETA. Rolfe, P. Brown, P. Carter, A. Gaberscik, L. Galbiati, B. Haist, R. Horn,M. Irving, D. Locke, A.B. Loving, P. Martin, S.F. Mills, R. Minchin, J. Palmer,S.'Sanders, S.G. Sanders, R. Stokes 36

The mega AMP spherical tokamakM.Cox 37

The design of the KSTAR TokamakG.S. Lee, J. Kim, C.S. Chang, H.Y. Chang, K. Kim, M.H. Cho, H.K. Park,G.H. Neilson, W.T. Reiersen, J. Schultz, L. Sevier, S.M. Hwang, D.K. Lee,D.I. Choi 38

Contributed Papers

Section A : Plasma Facing Components

Possibility of crack propagation in first wall by cyclic electromagneticforceT. Teramoto, Y. Utsugi, M. Saito 41

The effect of irradiation temperature and dose on the physical andmechanical properties of berylliumS.A. Fabritsiev, A.S. Pokrovsky 45

Beryllium armored mockups for fusion high flux applicationA. Gervash, R. Giniyatulin, I.V. Mazul, R. Watson 47

Non-destructive examination for Be/CuCrZr, W/Cu and Cu/CuCrZr jointsE. Kretov, K. Pavros, B. Karev, R. Giniyatulin 51

Complex investigation of several silverless brazed Be/CuCrZr jointsA. Komarov, A. Gervash, V. Komarov, I. V. Mazul, N. Litounovski, V. Fedotov,O. Sevrukov, A. Ganenko 53

Divertor experiment in the W7-AS stellaratorD. Dorst, P. Grigull, J. Kisslinger, K. McCormick, H. Niedermeyer, F. Sardei,F. Wagner 55

Experimental study of material response on simulated plasma disruptionloadV.N. Litunovsky, V.E. Kuznetsov, I.B. Ovchinnikov, V.A. Titov 59

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Alternative design proposal for CFC-monoblocks to be used in ITER highheat-flux componentsL. Giancarli, G. Le Marois, Y. Poitevin, P. Revirand, J.F. Salavy,J. Szczepanski 63

The first inspection of JT-60U W-shaped divert or after high poweroperationK. Masaki, K. Kodama, M. Morimoto, T. Sasajima, S. Takahashi, N. Hosogane,M. Saidoh 67

Development, Thermomechanical analysis, Fabrication and testing of amacroblock-divertor specimensM. Scheerer, H. Bolt, A. Gervash, J. Linke, R. Lison, I. Smid 71

Critical design issues of new semitransparent liner for ITER divertorcassette/. V. Mazul, C. Ibbot, R. Tivey, G. Federici, A. Makhankov, V. Odintsov,Ye. Kuzmin, V.M. Komarov, D. Serebrennikov, A. Zakharov, A. Gorodetsky,I. Markin 75

Manufacturing and testing of ITER divertor gas box linersI.V. Mazul, R. Giniyatulin, V.L. Komarov, V. Krylov, Ye. Kuzmin, A. Makhankov,V. Odintsov, A. Zhuk 77

Utilisation of resistive way for simulation surface thermal loadingN.V. Litunovsky, V.L. Komarov, I.V. Mazul, V.I. Smirnov 81

Some engineering aspects of high heat flux components for volumetricneutron source based on spherical torusV.V. Filatov, M.D. Korolkov, I.V. Mazul 83

Thermal fatigue and thermal shock of carbon based divertor componentsunder ITER relevant loading conditionsJ. Linke, R. Duwe, M. Rodig, B. Wiechers 87

Development of A1-Ge thixotropic alloys for plasma facing componentsF.L. Saint-Antonin, J. Valer, P. Meneses, M. Suery, G. Le Marois 89

Carbon Fiber Reinforced Copper as Heat Sink Material for DivertorApplicationsR Worgotter-Plunger, J. Korab, M. Scheerer, W. Hohenauer, I. Smid,M. Anwander, P. Sebo 93

Fabrication of a small-scaled first wall mock-up with beryllium armor hipbonded to DSCu/SS structure7. Hatano, 7. Kuroda, T. Iwatachi, 7. Osaki, M. Enoeda, H. Takatsu 97

XVIII

Study of material destruction during powerful plasma exposureV.G. Belan, assanein A., V.F. Levashov, V.S. Maynashev, A.D. Muzichenko,V.L. Podkovirov, A.M. Zitlukhin 101

Study of graphite erosion under lateral radiation from target plasmaV. Safronov, N. Arkhipov, V. Bakhtin, S. Kurkin, D. Toporkov, S. Vasenin,A. Zhitlukhin, H. Wuerz 105

Erosion products in disruption simulation experimentsV. Safronov, I. Arkhipov, N. Arkhipov, V. Bakhtin, V. Barsuk, S. Kurkin,E. Mironova, D. Toporkov, S. Vasenin, H. Werle, H. Wuerz, A. Zhitlukhin 107

Development of plasma facing components for fusion experimentalreactors in JAERIK. Sato, S. Suzuki, K. Ezato, K. Nakamura, M. Araki, M. Akiba 109

Development of bonding techniques of W and Cu-alloys for plasmafacing components of fusion reactor with HIP methodS. Saito, K. Fukaya, S. Ishiyama, M. Eto, K. Sato, M. Akiba 113

The Tore Supra toroidal pump limiter supporting structure :manufacturing and installationL. Doceul, J.J. Cordier, F. Faisse, P. Garin, L. Garampon, D. Lafon 117

Infrared non destructive test of plasma facing components. Defectdetection improvementA. Durocher, Ph. Chappuis, R. Mitteau, L. Moncel 121

Copper alloy-stainless steel bonds and recent developments for ToreSupraM. Lipa, Ph. Chappuis, R. Mitteau, L. Plochl, T. Huber, G. Reindl 125

Heat flux deposition pattern on the inner first wall of Tore SupraR. Mitteau, M. Chantant, Ph. Chappuis, D. Guilhem, M. Lipa 129

Active metal casting technique in plasma facing components :characterisationL. Moncel, J. Schlosser, R. Mitteau, L. Plochl 133

Thermal hydraulic testing for ITER high heat flux componentsJ. Schlosser, F. Escourbiac, M. Merola, G. Vieider 137

The pumping system for the CIEL project on Tore SupraE. Tsitrone, Ph. Chappuis, F. Escourbiac, F. Faisse, C. Portafaix, D. Reiter,J. Schlosser 141

Release of Deuterium from a-C:D-layers by oxygen attackS. Alberici, H.-K. Hinssen, R. Moormann, C.H. Wu 145

XIX

Small and medium scale mock-ups of the ITER divertor wingM. Grattarola, M. Bet, M. Merola, G.B. Ottonello, L. Plochl, B. Riccardi,ASalito, G. Vieider, F. Zacchia 149

Tritium Experience in the Tokamak Fusion Test ReactorC.H. Skinner, W. Blanchard, J.N. Brooks, J. Hogan, J. Hosea, D. Mueller,A.Nagy 153

Thermal annealing of irradiated carbon fiber composites used as plasmafacing materialsJ.P. Bonal, C.H. Wu 157

Disruption and erosion on plasma facing materials with Oarai hot-cellelectron beam irradiating system (OHBIS)M. Uda, E. Ishitsuka, K. Sato, M. Akiba, C. Yamamura, S. Takebayashi,H. Kawamura 161

Numerical simulation of the internal stresses of thick tungsten coatingdeposited by vacuum plasma spraying on copper substrateA Salito, M. Tului, F. Casadei 165

Design and testing of protective graphite shield for Tokamak-15discharge chamber and moveable electrodes for glow dischargeP.P. Khvostenko, E.V. Alexandrov, I.O. Anashkin, V.N. Garnov, V.A. Khrabrov,V.A. Kochin, V.M. Leonov, P.N. Orlov, I.A. Posadsky, A.N. Vertiporokh 169

The Effects of HIP Thermal Cycles and Neutron Irradiation on Metallurgyand Fracture Toughness of Cu/SS JointsM. Pyykkonen, S. Tahtinen, B.N. Singh, P. Toft 173

Fracture strength of DS-Cu/316SS HIP bonded structureM. Goto, M. Uno, M. Saito, T. Hatano 177

Effect of electromagnetic force on strength of bonded joint withinterfacial crackS. Yamashita, T. Teramoto, M. Saito 181

Recent results of EU R&D on removal of co-deposited layers and tritiumC.H. Wu, A.A. Haasz, W. Jacob, R. Moormann, V. Philipps, J. Roth 185

High heat flux testing of a prototypical divertor componentM. Merola, F. Escourbiac, L. Plochl, R. Raffray, J. Schlosser, I. Smid,R. Vesprini, G. Vieider 189

Properties of beryllium as a high heat flux material before and after: neutron irradiationr M. Rodig, R. Duwe, J. Linke, A. Lodato 193

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The EU HT test programme of ITER primary wall small scale mock upsP. Lorenzetto, A. Cardella, Ph. Chappuis, W. Daenner, M. Febvre,G. Hofmann, H. Stamm, S. Tahtinen, G. Walsh 19.

The ITER post limiter systemA. Cardella, K. loki, G. Janeschitz, A. Lodato, H.D. Pacher, R.R. Parker,R. Raffray, V. Rozov, K. Skladnov 19

The attachment system of the ITER divertor plasma facing componentsS. Chiocchio, A. Turner, G. Cerdan, H. Heidi, R. Jakeman, D. Maisonnier,A. Poggianti, M. Siuko, R. Tivey 20

Solid, castellated, lamellar, and brush-like armours for the high heat fluxcomponents of ITERR. Matera, V. Barabash 2C

Effect of runaway electrons and VDE's on ITER first wallA.R. Raffray, M. Akiba, A. Cardella, K. Ezato, G. Federici, K. loki, R.R. Parker,L. Topilski 21

Joining technologies for the plasma facing components of ITERV. Barabash, G. Kalinin, R. Matera 2\

Study of residual stresses in electron-beam welded F82H modifiedmartensitic steel using X-ray and neutron diffractionR. Coppola, C. Braham, M. Ceretti, C. Nardi 2

Tungsten thick coatings for plasma facing componentsB. Riccardi, A. Pizzuto, A. Orsini, S. Libera, E. Visca, L. Bertamini, F. Casadei,E. Severini, R. Montanari, R. Vesprini, P. Varone, G. Filacchioni,N.V. Litunovsky 2.

Thermal fatigue equipment to test joints of materials for high heat fluxcomponentsE. Visca, S. Libera, A. Orsini, B. Riccardi, M. Sacchetti 2

Deuterium retention in beryllium exposed to a 60 kV deuterium beam -consequences for next step devicesH.D. Falter, J.P. Coad, D. Ciric, D.J. Godden 2

Depostits/flakes in the JET Mklla divertor - a major source of Tritium andDeuterium inventoryA.T. Peacock, P.A. Andrew, J.P. Coad, R. Cusack, F.H. Hurd, S.F. Mills,R.D. Penzhorn, M. Pick 2

The recycling parameters of MANET exposed to deuterium plasma and afurther evaluation of the tritium tracking at the DEMO-First WallL.A. Sedano, J. Camposilvan, A. Perujo 2

XXI

High heat flux performance of mechanically jointed divertor plate for LHDY. Kubota, N. Noda, S. Inagaki, R. Sakamoto, A. Sagara, S. Satoh,0. Motojima 241

Disruption simulation experiments and extrapolation to reactorconditionsA.B. Hassanein, I. Konkashbaev 245

Development of divertor targets for Wendelstein 7-XH. Greuner, A. Herrmann, H. Renner, Ph. Chappuis, R. Mitteau 249

Thermal load calculations at TJ-11 vacuum vessel under NBIJ. Guasp, M. Liniers, C. Fuentes, G. Barrera 253

Design of an improved first wall for RFXP.Zaccaria, W. Baker, S. Peruzzo, P. Sonato 257

Helium and tritium behaviour in neutron irradiated berylliumIB. Kupriyanov, V.V. Vlasov 261

Non-Brazed Plasma Facing Component for high steady state heat fluxB. Streibl, H. Greuner, A. Herrmann, S. Kotterl, S. Mukherjee, S. Schweizer,J. Simon-Weidner, H. Euringer, J. Linke, M. Sauer, M. Scheerer, R. Uhlemann,Ph. Chappuis, M. Lipa, R. Mitteau 263

Development and optimisation of tungsten armour geometry for ITERdivertorA. Makhankov, I.V. Mazul, V. Safronov, N. Yablokov 267

A consistent 2D analysis of erosion of the ITER slot divertorH. Wurz, S. Pestchanyi, B. Bazylev, F. Kappler 271

Numerical simulation of brittle destruction and of carbon based materialsdue to pulsed plasma heatingS.E. Pestchanyi, N.A. Usov, H. Wuerz 275

Evaluation of Tungsten and other refractory materials as a facingmaterial for the ITER divertor and first wallA. Karasiov, S.A. Fabritsiev 279

Section B : Plasma Heating and Current Drive

A design of an ECRH launcher for ITERO.G. Kruijt, P.R. Prins, A.G.A. Verhoeven, F.J. van Amerongen, W.A. Bongers,LdeJong, R.P.J.J.M. Kruisbergen, M.A. Makowski, E. Woldberg 283

Feed back controls on Tore Supra ICRH antennae for High PowerperformancesL Ladurelle, C. Munnier, G. Agarici, B. Beaumont, S. Bremond,J.M. Delaplanche, G. Lombard, P. Mollard 287

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Alfven wave spectrum control in the heating and current driveexperimentsLF. Ruchko, E. Lerche, R.M.O. Galvao, E. Ozono, A.N. Fagundes,I.C. Nascimento 291

Radiation induced power loss in insulating gases for ITER NBI systemsE.R. Hodgson, A. Morono 295

ECRH system for the W7-X stellaratorV. Erckmann, T. Geist, H.P. Laqua, M. Weissgerber 299

Design Characteristics of the Ion Cyclotron System for the KSTARTokamakB.G. Hong, Y.D. Bae, C.K. Hwang, J.G. Kwak, M.H. Ju, D.W. Swain,P.M. Ryan, B.W. Riemer 303

Neutral beam injection system for TJ-IIM. Liniers, J. Alonso, L. Martinez-Laso, J. Doncel, A. Garcia, M. Medrano,J. Guasp, C. Fuentes, C.C. Tsai, G.C. Barber, S.L. Milora, C. Alejaldre 307

RF systems on SST1 tokamakD. Bora, P.K. Sharma 311

3MW, 110 GHz ECH system for the Dlll-D tokamakR.W. Callis, J. Lohr, D. Ponce, T.E. Harris, R.C. O'Neill, D.B. Remsen,R. Prater, T.C. Luce 315

A steerable ECRF launcher for ITERH.J. Grunloh, R. Prater, J.L Doane, C.P. Moeller, M. Makowski 319

RF circuit concept for a diacrodeC. Robert, G. Clerc, J.P. Ichac, A. Boussaton 323

Coupling Characteristics of a Helicon Antenna in KAIST-Tokamak PlasmaS.J. Jeon, W. Choe, G.C. Kwon, J.H. Kim, H.S. Yi, .W. Hen, H.Y. Chang,D.I. Choi 327

Actively cooled guard limiters for Tore Supra ICRH and LHCD antennasG. Agarici, B. Beaumont, Ph. Bibet, S. Bremond, J.M. Delaplanche,L. Garampon, 7. Huber, L. Ladurelle, G. Lombard, P. Mollard, C. Patterlini,L Plochl 331

The power measurement system of the Tore Supra ECRH transmitter at118 GHzG. Berger-By, J.P. Crenn, M. Pain, D. Roux 335

Advanced launcher for lower hybrid current drive on Tore SupraPh. Bibet, F. Kazarian, G. Agarici, C. Deck, L. Doceul, Ph. Froissard,L. Garampon, M. Goniche, J. Mailloux, C. Portafaix, G. Rey, F. Samaille,J. Simoncini, G. Tonon, M. Durand, A. Vial, E. Rousset 339

XXIII

Vacuum tuner prototype development for ITER and Tore Supra ICRFlauncherS. Bremond, F. Durodie, G. Agarici, B. Beaumont, G. Bosia 343

Beam optics of the SINGAP 1MeV 100 mA D- dc acceleratorJ. Bucalossi, C. Desgranges, M. Fumelli, R.S. Hemsworth, P. Massmann,A. Simonin 347

Lower hybrid heating and current drive design for ITER and applicationfor present tokamaksPh. Froissard, G. Rey, Ph. Bibet, G. Bosia, L. Bruno, M. Goniche, F. Kazarian,S.Kuzikov, C. Portafaix, G. Tonon, F. Wasastjerna 351

RF test of a TE30 hyperguide for a lower hybrid antennaM. Goniche, P. Schild, Ph. Bibet, J. Plancoulaine, C. Portafaix, G. Rey,F.X.Sdldner 355

Testing of the 118 GHz-quasi CW gyrotron for the Tore Supra and TCVtokamaksM. Pain, P. Garin, M.Q. Tran, S. Albert!, M. Thumm, E. Giguet, P. Thouvenin,C. Tran 359

The drift source : a negative ion source module for DC multi-amperes ionbeamsA. Simonin, G. Delogu, C. Desgranges, M. Fumelli 363

Long pulse extraction of deuterium negative ion beams from theKamaboko ion sourceR. Trainham, C.Jacquot, Y. Fujiwara, Y. Okumura 367

Operation of 15MW Negative-Ion-Based Neutral Beam Injection SystemFor the Large Helical DeviceY. Oka, Y. Takeiri, K. Tsumori, O. Kaneko, M. Osakabe, E. Asano,T. Kawamoto, R. Akiyama 371

A regulated High-Voltage Power Supply for ICRH Amplifiers in Class COperation for ITERJ. Alex, P. Thomann 375

Test of the quasi-optical ECRH launching sytem for Frascati TokamakupgradeA Bruschi, R. Bozzi, S. Cirant, F. Gandini, G. Granucci, S. Mantovani,V. Mellera, V. Muzzini, A. Nardone, A. Simonetto, C. Sozzi, N. Spinicchia 379

Prototype design of the ITER ICRF vacuum transmission line dielectricwindow

I J. Linden, L. Heikinheimo, J.A. Heikkinen, M. Kemppainen, S. Orivuori,IM. Peraniitty, S. Saarelma, S. Tahtinen, F. Wasastjerna, G. Bosia 383

XXIV

Neutral Beam Injection on MASTM.P.SNightingale, S.E.V. Warder, D.C. Codling, R.T.C. Smith, M. Hill,S.J. Gee 387

Progress of negative-ion based NBI system for JT-60UM. Kuriyama, N. Akino, N. Ebisawa, L. Grisham, A. Honda, 7. Itoh, M. Kawai,M. Kazawa, M. kusaka, H. Liquen, K. Mogaki, 7. Ohga, K. Ohmori,K. Ohshima, Y. Okumura, H. Oohara, F. Satoh, H. Seki, anal, Y. Toyokawa,K. Usui, K. Watanabe, M. Yamaguchi, H. Yamazaki, 7. Yamazaki 391

Improvement of the ion source power supply for JT-60 negative-ionbased NBIK. Omori, K. Usui, K. Ohshima, 7. Ohga, M. Kawai, K. Watanabe, T. Itoh,M. Kuriyama, Y. Ono, S. Kawashima 395

Operation of the RF-System for the ECRH experiments on FTU tokamakG. Granucci, C. Sozzi, B. Berardi, R. Bozzi, A. Bruschi, G. Ciccone, S. Cirant,S. Di Giovenale, F. Gandini, S. Lupini, V. Mellera, V. Muzzini, A. Nardone,A. Simonetto, N. Spinicchia, M. Zerbini 399

Complex for ECRH and ECCD experiments on TJ-IIR. Martin, K. Likin, A. Fernandez, N.V. Matveev, J.R. Cepero 403

The vacuum insulated beam source for the ITER neutral beam injectionsystemE. Di Pietro, P.L. Mondino, T. Inoue, A. Krylov, P. Bayetti, P. Massmann,E. Hogdson, Y. Okumura, Y. Watanabe, Y. Fujiwara, E. Murasaka 407

Radiation analysis of the ITER neutral beam system7 Inoue, K. Shibata, E. Di Pietro, Y. Fujiwara, R.S. Hemsworth, E.R. Hodgson,H. lida, A. Krylov, P.L. Mondino, Y. Okumura, P. Bayetti, R.T. Santoro 411

Development of high power gyrotron and transmission line forECH/ECCD systemK. Takahashi, K. Sakamoto, A. Kasugai, M. Tsuneoka, Y. Ikeda, 7 Imai,T. Kariya, Y. Mitsunaka 415

Engineering issues of a 1000 S neutral beam ion sourceP.K. Jayakumar, M.R. Jana, N. Bisai, M. Bajpai, N.P. Singh, U.K. Baruah,A.K. Chakraborty, M. Bandyopadhyay, C. Chakrapani, D. Patel, G.B. Patel,P.J. Patel, V. Prahlad, N.V.M. Rao, C. Rotti, V. Sreedhar, S.K. Mattoo 419

Simulations and experiments on a multi-beam waveguide ECRHtransmission systemG. Gantenbein, L. Empacher, V. Erckmann, F. Hollmann, W. Kasparek,M. Weissgerber, H. Zohm 423

XXV

Ferrite hybrid system for generator matching in the ICRFW. Arnold, J.S. De Grassie, D.B. Remsen, E. Pivit, R. Russell, F. Braun 427

Progress of the "Batman" RF source for negative hydrogen ionsP. Frank, J. Bucalossi, B. Heinemann, W. Kraus, F. Probst, E. Speth,R. Trainham, O. Vollmer 429

Large-area, high-transparency extraction system for negative ionsB. Heinemann, J. Bucalossi, P. Frank, R. Riedl, A. Simonin, E. Speth,0. Vollmer 433

Matching considerations in an ICRH-system with hybrid couplersF. Hofmeister, F. Braun, H. Faugel, D. Hartmann, J.-M. Noterdaeme,F. Wesner 437

An RF source optimized for low pressure operationW. Kraus, P. Frank, B. Heinemann, R. Riedl, E. Speth, O. Vollmer 441

An injection system for off-axis NBCD on ASDEX UpgradeR. Riedl, A. Stabler, B. Heinemann, J. Sielanko, E. Speth 445

Commissioning and performance of the new ASDEX Upgrade neutralbeam injectorO. Vollmer, A. Stabler, E. Speth, M. Ciric, P. Franzen, B. Heinemann,W. Kraus, W. Melkus, R. Riedl, W. Scharich 449

High RF power test of a CFC antenna module for lower hybrid currentdriveS. Maebara, M. Seki, Y. Ikeda, K. Kiyono, K. Suganuma, 7. Imai, M. Goniche,Ph. Bibet, rossaud J. , ano V., F. Kazarian-Vibert, Ph. Froissard, G. Rey 453

Radio frequency auxiliary heating systems design in ITERM. Makowski, G. Bosia, C. Caroli, F. Elio, Ph. Froissard, 7. Kodama, Y.U. Utin 457

New design for t the anode power supply of a gyrotronD. Fasel, S. Albert!, A. Favre, A. Perez, J. Acero, D. Ganuza, I. Garcia,C. Lucia 461

Toward an active passive waveguide array for lower hybrid applicationon ITERF. Mirizzi, C. Gourlan, A. Marra, M. Roccon, A.A. Tuccillo, Ph. Bibet,Ph. Froissard, M. Goniche, F. Kazarian-Vibert, J. Mailloux, G. Rey,J. Simoncini 465

Space and time resolved doppler spectroscopy of neutral beamsD. Ciric, H.D. Falter, D.J. Godden 469

XXVI

Operating experience with the JET tritium neutral beam injector7.7.C. Jones, A.J. Bickley, CD. Challis, S.J. Cox, H.P.L. De Esch,D.J. Godden, D. Stork, S.L. Svensson, D. Young

Compensation for non-linear interaction between JET NBI deflectionmagnets for simultaneous D2/T2 beamline operationH.P.L DeEsch

Isoptope exchange in high heat-flux components of the JET tritiumneutral beam injectorD. Ciric, H.P.L. De Esch, H.D. Falter, T.T.C. Jones, L. Svensson

Intervention to repair a tritiated JET neutral beam injectorM.J. Watson, A.C. Bell, A.J. Dines, F.H. Hurd, J.G. Lunquist, B.J. Macklin,J.C. Orchard, B. Patel

Advanced high power gyrotrons for ECRH applicationsM. Kuntze, E. Borie, O. Braz, G. Dammertz, S. Illy, G. Michel, A. Mobius,B. Piosczyk, M. Thumm

Development of a 1 MeV H- beam accelerator for neutral beam injectorK. Watanabe, Y. Fujiwara, M. Hanada, 7. Inoue, K. Miyamoto, N. Miyamoto,Y. Okumura, K. Satoh

Initial tests of the ITER R&D prototype ion cyclotron antennaD.W. Swain, R.H. Goulding, P.M. Ryan, J.B. Wilgen

.473

.477

.481

. 485 \

.489

.493

.497

The fusion-FEM : 0,75 MW of mm-wave powerP.H.M. Smeets, W.A. Bongers, V.L. Bratman, S. Brons, M. Caplan,G.G. Denisov, C.A. Van_der Geer, K.L. Lingier, P. Manintveld, J. Plomp,J. Pluygers, A.J. Poelman, A.V. Savilov, A.B. Sterk, A.A. Varfolomeev,A.G.A. Verhoeven, W.H. Urbanus 499

Engineering issues for the design of the heat removal system and thecryo system for the 1000 s neutral beam injector for SST-1P.K. Jayakumar, C. Chakrapani, N. Bisai, M. Bandyopadhyay, C. Rottii,B. Sreedhar, N.V.M. Rao, A.K. Ckakraborty, M.R. Jana, V. Prahlad,U.K. Baruah, D. Patel, G.B. Patel, N.P. Singh, S.K. Mattoo

Section C : Plasma Engineering and Control

ITER model reduction by Selective Modal AnalysisA. Beghi, D. Ciscato, M. Cavinato, G. Marchiori

503

507

Implementation of advanced plasma control techniques for next-generation tokamaksD.A. Humphreys, T.E. Evans, J.R. Ferron, A.W. Hyatt, A.G. Kellman,J.A. Leuer, B.G. Penaflor, M.L. Walker, T.C. Jernigan, D.G. Whyte,R.S. Granetz, R.R. Khayrutdinov, V.E. Lukash, Y. Neyatani, R. Yoshino 511

XXVII

A systematic approach to error field analysis in ITERJ.A. Leuer, R.J.- La Haye, A.G. Kellman, D.A. Humphreys, J.T Scoville,Y. Gribov, J.C. Wesley, R. Buttery, T. Hender, N. Doinikov 513

Application of Sequential Function Chart Methodology to ITER ControlSystem/. Yonekawa, J.Y. Journeaux, Y. Matsumoto 517

Progress in shape control at ASDEX upgradeW. Treutterer, O. Gruber, P.J. McCarthy, G. Raupp 521

Control and communication system for plasma heating unit and powersupply system of large helical deviceC. Takahashi, R. Akiyama, T. Inoue, S. Takami, F. Shimbo, K. Haba,Y. Takita, E. Asano, G. Nomura, S. Ito, T Komoto, Y. Taniguchi, H. Ogawa,N. Yamamoto, H. Chikaraishi, 7 Mutoh, S. Kubo, H. Idei, Y. Takeiri, O. Kaneko,K. Watanabe, H. Yamada, S. Tanahashi, K. Yamazaki, K. Mural, T. Watari,0. Motojima 525

ITER poloidal field system requirements for steady state reversed shearscenariosV. Grandgirard, J.M. Ane, M.R. O'brien, X. Garbet, X. Litaudon, B. Lloyd,H. Lutjens, D. Moreau, C. Roach, I. Voitsekhovitch, C. Warrick, M. Zabiego 529

A long-period analog integrator for magnetic measurements in ToreSupraM. Prou, E. Barth, B. Couturier, P. Ouvrier-Buffet 533

Automatic real-time protection reflexes to counteract instabilities7 Zehetbauer, G. Neu, M. Maraschek, V. Mertens, G. Raupp, W. Treutterrer,D.Zasche 537

The Mast plasma control systemG.J. Me Ardle, V.A. Belyakov, A. Kavin, P.J. Knight, A. W. Morris,D.A. Ovsyanikov, E.N. Rumyanysev, D.L. Trotman, E. Veremey,J. Waterhouse 541

Reduction of toroidal magnetic field ripple in the advanced materialtokamak experiment on JFT-2MM. Sato, Y. Miura, H. Kimura, M. Yamamoto, T. Koike, T. Nakayama,M. Hasegawa, K. Urata 545

Conceptual design of KSTAR plasma control systemY.S. Hwang, M.C. Kim, B.J. Lee, M.C. Kyum, J.Y. Kim 549

System of external windings for control of the plasma stability intokamak T-10P.V. Savrukhin, S.V. Tsaun 551

XXVIII

Analysis of tolerances and error fields for the ITER magnet systemC. Sborchia, E. Zapretilina, A. Alekseev, N. Doinikov, Y. Gribov, S. Krasnov,B. Mingalev, N. Mitchell, B. Stepanov, K. Yoshida 555

Plasma modelling for position and shape control in TCVP. Vyas, R. Albanese, G. Ambrosino, M. Ariola, I. Bandyopadhyay, A. Coutlis,D.J.N. Limebeer, J.B. Lister, F. Villone, J.P. Wainwright 55£

The new FTU feedback control system : an approach oriented to thefuture plasma equilibrium configurations on FTUV. Vitale, G. Buceti, C. Centioli, S. Ciattaglia, F. Crisanti, G. D'Antona,G. Mazza, C. Neri, M. Riva 56L

Control of the vertical instability in the high aspect ratio (A=5.5)elongated FTU plasmasM. Santinelli, W. Cocilovo, F. Crisanti, V. Riccardo 56',

Interlock and protection systems for JET in-vessel cooling and cryogeniccomponentsD. Stork, P. Ageladarakis, A.C. Bell, T.A. Browne, 7 Budd, P.R. Butcher,N. Dolgetta, C.G. Elsemore, S. Papastergiou, R.J.H. Pearce, D. Young 57

The JET level-1 softwareP.A. Me Cullen, J.W. Farthing 57:

Design and implementation of a real-time power control system at JET7 Budd, H. Brelen, Q. King, N. Zorning 57:

Digital local control system of radial magnetic field errors in RFX :design, commissioning and first operationE. Gaio, A. Luchetta, G. Manduchi, G. Marchiori, V. Toigo 58.

ITER scenario simulations with a non-linear MHD equilibrium codeM. Cavinato, G. Marchiori, A. Beghi, D. Ciscato, A. Portone 58

Optimal design of the poloidal gap of a conductive shell for a RFPA. Masiello, G. Zollino 59

Plasma current, position and shape control for ITERP.L. Mondino, R. Albanese, G. Ambrosino, M. Ariola, A. Beghi, D. Ciscato,E. Coccorese, Y. Gribov, D. Humphreys, A. Kavin, C. Kessel, R. Khayrutdinov,J.B. Lister, V.E. Lukash, Y. Mitrishkin, L.D. Pearlstein, A. Pironti, A. Portone,I. Senda, 7. Shoji, P. Vyas, M.L. Walker 59

Application of HTSC coils for mitigation of VDE during a major disruption7. Yamada, 7. Uchimoto, K. Miya, Y. Nakamura 5S

XXIX

Section D : Experimental Systems and Diagnostics

Diagnostic neutral beam injector with RF plasma emitterI.V. Shikhovtsev, G.F. Abdrashitov, VS. Belkin, A.I. Gorbovsky,V.I. Davydenko, P.P. Deichuli, A.N. Dranichnikov, A.A. Ivanov, V.A. Kapitonov,V. Ya. Kremyansky, V. V. Mishagin, A.A. Podminogin, V. Ya. Savkin,A.V. Sitnikov, R. Uhlemann 605

Characteristics of a large reversed field pinch machine, TPE-RXY. Yagi, T. Shimada, Y. Hirano, S. Sekine, H. Sakakita, H. Koguchi, S. Kiyama,Y. Maejima, I. Hirota, K. Hayase, Y. Sato, K. Sugisaki, I. Oyabu, M. Hasegawa,M. Yamane, F. Sato, K. Kuno, 7. Minato, A. Kiryu, S. Takagi, K. Sako,F. Kudough, K. Urata, J. Orita, H. Kaguchi, H. Sago, K. Ue 609

New instrumentation to characterize the electron velocity distribution inthe TEXTOR tokamakB.S.Q. Elzendoorn, A.J.H. Donne, C.J. Barth, C. Domier, G. Van Dijk, J.C. vanGorkom, J.A. Hoekzema, C.A. Hugenholtz, O.G. Kruyt, H.J Van der Meiden,T. Oyevaar, P.R. Prins 613

Design and manufacturing of vacuum vessel of TPE-RXH. Sago, H. Kaguchi, J. Orita, Y. Ishigami, K. Urata, M. Hasegawa, Y. Yagi,Y. Hirano, T. Shimada, S. Sekine, H. Sakakita 617

Feedthrough for the Actively cooled Dynamic Ergodic Divertor Coils atTEXTOR 94M. Poier, A. Charl, B. Giesen 621

Possible applications of powerful pulsed CO2-LASERS IN TOKAMAKREACTORSFEASIB CO2 -lasers in Tokamak reactorsA.F. Nastoyashchii, I.N. Morozov, assanein A 625

Plasma equilibrium diagnostics and control in TCABR TokamakYu. K. Kuznetsov, I.C. Nascimento, R.M.O. Galvao, L.F. Ruchko, A.G. Tuszel,R.P. Da Silva, A.M.M. Fonseca, A.P. Dos Reis, E.K. Sanada 629

Plasma boundary diagnostics in ITER:error analysisYu.K. Kuznetsov, I.C. Nascimento, R.M.O. Galvao 633

Calorimetric measurement results on Tore SupraM. Chantant, A. Grosman, Ph. Ghendrih, F. Surle 637

The Tore Supra ergodic divertor from design to experimentPh. Ghendrih, A. Grosman, J.J. Cordier, L. Gargiulo, G. Agarici, B. Bertrand,L. Doceul, M. Lipa, R. Mitteau 641

Tore Supra - a new conditioning procedure in the presence of thetoroidal fieldC. Grisolia, G. Martin, F. Saint-Laurent 645

XXX

The Tore Supra centralised control systemJ.Y. Journeaux, F. Parlange, G. Martin 649

Tore Supra : the real time plasma control systemD. Moulin, B. Couturier, L. Ducobu, D. Elbeze, B. Guillerminet, M. Leluyer,F. Leroux, P. Pastor, P. Spuig 653

Real time measurement of the position, density profile and current profileat Tore SupraF. Saint-Laurent, C. Gil, P. Houy, E. Joffrin, G. Martin, D. Moulin 657

Evolution of hydraulic system for moving components on Tore SupraF. Samaille, J.Y Journeaux, L. Doceul, G. Giraud, G. Pasquier 661

The Tore Supra cooling system : 10 years of operationF. Surle, G. Mayaux, M. Chantant, J. Malagoli, D. Monbrun, P. Patier, B. Thos 665

Networked remote control and data acquisition on the MANTIS test standR. Trainham, C. Jacquot 669

The MAST Data Acquisition SystemJ. Waterhouse, S.J. Manhood 673

Control and data acquisition on a laser in-vessel viewving systemR.C. Pereira, N. Cruz, C. Correia, C. Neri, M. Riva, A. Coletti, C.A.F. Varandas 675

Laser beam transport system for LHD THOMSON scatteting diagnosticK. Yamauchi, H. Hayashi, M. Kojima, K. Murai, K. Narihara, I. Yamada,H. Nakanishi, 7. Minami 679

Acceptable manufacturing accuracy of components used to build up thestellarator W7-XB. Sombach, J.H. Feist, H. Schneider, J. Simon-Weidner 683

Amplitude - modulated laser in vessel viewing system (LIVVS) for ITER /JETL. Bartolini, A. Coletti, M Ferri de Collibus, G. Fornetti, C. Neri, M. Riva,L. Semeraro, C. Talarico 685

JET reliability assessment for 4T operation and the DTE1 3.8T experienceS. Papastergiou, E. Bertolini, M. Buzio, A. Kaye, J. Last, P. Miele, V. Riccardo 689

Diagnostic experience during Deuterium-Tr itium experiments in JET,techniques and measurementsA. Maas, P.A. Andrew, P. Coad, A. Edwards, J. Ehrenberg, A. Gibson,K. Gunther, M.G. Von Hellermann, D. Hillis, A. Howman, O.N. Jarvis,J.F. Junger, R.W.T. Konig, J. Lingertat, M.J. Loughlin, P.D. Morgan,J.C. Orchard, G.J. Sadler, M.F. Stamp, C. Wilson 693

XXXI

Recent Results on ITER Plasma Equilibrium Diagnostics andIdenfificationR. Albanese, E. Coccorese, P.J. Me Carthy, F.C. Morabito, A. Pironti,M. Versaci 697

Commissioning and operation of the ground loops detection system ofRFXN. Pomaro, F. Bellina 701

Section E : Magnets and Power Supplies

Realization of fast reversal time for toroidal field in TPE-2MV. Sato, S. Kiyama, K. Hayase 707

New proposal to estimate the current distribution in the CICC cross-sectionV. Amoskov, E. Lamzin, S. Sytchevskij, M. Zhelamskij, S. Egorov 711

The first experimental observation of the He mass exchange betweencable space and central channel in CICC obtained by SHF method duringQUELLN. Shatil, M. Zhelamskij, A. Anghel, G. Vecsey, Y. Takahashi, K. Hamada 715

The coil system of a helias reactorE. Harmeyer, O. Jandl, H. Wobig 719

Design of equilibrium field control coil system of TPE-RXF. Sato, M. Hasegawa, M. Yamane, I. Oyabu, K. Urata, F. Kudough, 7. Minato,A. Kiryu, S. Takagi, K. Kuno, K. Sako, Y. Hirano, Y. Yagi, 7 Shimada,S. Sekine, H. Sakakita 723

Magnetization and loss measurements of short samples of Nb3Sn roundwires using hall probes and a standard magnetization techniqueM. Foitl, A. Kasztler, H. Kirchmayr, L. Krempasky, J. Kvitkovic, M. Polak 727

Development, Design and Fabrication of Coil Casing and Embedding forthe Wendelstein 7 - X Demo CoilH. Kronhardt, K.D. Herrmann, H. Klunker 731

Design and Manufacturing of a Wendelstein 7-X Demonstration CoilH. Kronhardt, O. Dormicchi, J. Sapper 735

The preparations for testing the ITER toroidal field model coil (TFMC)A. Ulbricht, M. Darweschsad, J.L. Duchateau, H. Fillunger, S. Fink,G. Friesinger, R. Heller, P. Hertout, P. Libeyre, G. Noether, S. Raff,F. Wuechner, G. Zahn 739

XXXII

Development of an IGBT converter for a magnet power supplyY.M. Miura, M. Matsukawa, 7 Kimura 743

Structural Analysis of the ITER CryostatM. Verrecchia, P. Barabaschi, R. Haange, Y. Nagashima 747

10 kA range current lead for SST-1A. Amardas, B. Sarkar, L. Vipul, V.L. Tanna, Y.C. Saxena 751

Power Supply and Quench Protection for the WENDELSTEIN 7-X MagnetA. Nitsche, J. Sapper 755

Current control of superconducting coils of LHDH. Chikaraishi, S. Yamada, O. Motojima, T. Sato, K. Tomatsu, H. Niwa,7 Haga 759

New magnetic measurement of the Tore Supra toroidal field profileJ.J. Cordier, P. Hertout, L. Gargiulo, V. Cantone, B. Soler 763

From conceptual to engineering design of the ITER TFMCP. Libeyre, B. Crepel, P. Decool, H. Fillunger, B. Glassl, U. Hoeck, R. Kreutz,R. Maix, R. Meyer, R. Penco, S. Raff, E. Theisen, N. Valle 767

Hydraulics of the ITER toroidal field model coil cable-in-conduitconductorsS. Nicollet, H. Cloez, J.L. Duchateau, J.P. Serries 771

Conductor fabrication for the HT-7U model coilB. Li, S.T. Wu, W.Y. Wu, Y.F. Bi, P.D. Weng, Z. Chen, Y.N. Pan, D. Wu,Y.H.Zhu 775

Design and construction of cryogenic supporting structures for LHDS. Imagawa, H. Tamura, A. Nishimura, 7 Satow, S. Satoh, O. Motojima 779

ITER magnetic system candidates low friction materials tested undervacuum at cryogenic temperatureL.F. Moreschi, S. Storai, A. Pizzuto, A. Orsini, P. Zbigniew, G. Malavasi 783

Design and construction of AC loss measuring systemJ. Li, G. Zhang, Y. Pan, Y. Zhu, B. Li, Z. Chen, S. Wu, W. Wu, X. Wu 787

Consideration of high Tc superconductor application to magnets fortokamak fusion reactors7 Ando, 7 Isono, H. Nakajima, M. Kikuchi, H. Tsuji 791

Optimization of the protective energy removal parameters for tokamakHT7-U superconducting magnetsP.P. Khvostenko, Y.F. Bi, S.M. Cheng, A.N. Chudnovsky, Y.X. He,I.A. Posadsky 795

XXXIII

Toward less expensive conductors for the ITER magnetsD. Bessette, N. Mitchell 799

ITER central solenoid model coil fabrication and implications for the fullscale central solenoidR.J. Thome, K. Okuno, R. Vieira, D. Bessette, Z. Piec, R. Jayakumar,N. Martovetsky, J. Wohlwend, H. Tsuji, T. Ando, H. Nakajima, 7. Kato 803

Electrical insulation design and monitoring of the ITER magnet systemK. Yoshida, F. lida, R. Gallix, S. Sadakov, R. Vieira, J. Stoner, C. Sborchia 807

Integrated protection for the ITER coils and power suppliesP.L. Mondino, B. Bareyt, I. Benfatto, N. Britousov, C. Neumeyer, A. Roshal 811

Calculations for the optimization of the external connections of theDynamic-Ergodic-Divertor of Textor-94D. Styhler, U. Braunsberger, B. Giesen, M. Lindmayer, O. Neubauer 815

Support system for the W7-X coil assemblyN. Jaksic, J. Simon-Weidner, J. Sapper 819

Fast evaluation of W7-X components with aspects of safety based on FE-calculationsJ. Simon-Weidner, N. Jaksic 823

Manufacture of the MAST centre rod and ohmic heating solenoidJ. McKenzie, G. Voss 827

The RTP chopper-regulated, voltage-smoothed power suppliesJ. Lok, A. Agterberg, B. De Groot, M. Kaay, A.B. Sterk, A. Verheul 829

Manufacture of the ITER TF model coilR. Maix, G. Di Bartolo, G. Bevilacqua, P. Libeyre, P. Decool, A. Ulbricht,B. Schellong, A. Bourquard, B. Crepel, N. Valle, P. Pesenti, E. Theisen 833

A new flywheel for the TCV turbo-generatorA Perez, E. Beaumont, P. Bey, R. Chavan, C. W. Hustad, D. Fasel, A. Favre,F. Picard, J.J. Simon, H. Sprysl 837

Successfull completion of the conductor manufacture for the ITER TFmodel coilA Delia Corte, M. Ricci, M. Spadoni, G. Bevilacqua, R. Maix, E. Salpietro,S. Conti, R. Garre, S. Rossi 841

Mechanical assessment of the JET TF coils for 4T upgrade : the new 3Dhybrid modelP. Miele, E. Bertolini, M. Buzio, A. Kaye, J. Last, S. Papastergiou, V. Riccardo 845

XXXIV

The upgrade of the JET toroidal field power supplies for the 4 teslaoperation7 Bonicelli, D. Chiron, P. Doyle, M. Huart, A. Paynter, P. Smith 849

New power supply to generate a rotating toroidal field in RFXPi. Piovan 853

Large coil modelling for fast transient simulationsA. De Lorenzi, P. Bettini, G. Chitarin 857

Main technological aspects of the ITER AC/DC converter systemE. Gaio, A. Maschio, R. Piovan, V. Toigo, G. Candela, A. Coletti, I. Benfatto,P.L. Mondino, A. Roshal, P. Bordignon, A. Galli, A. Piazzesi 861

Development of the KSTAR CS (central solenoid) model coilS.H. Kim, Y.H. Kim, Y.H. Kim, H.S. Kim, K.H. Chung 865

Mechanical deformation of the large helical device during cooling-downand excitation testsA. Nishimura, H. Tamura, S. Imagawa, S. Satoh, O. Motojima 869

Mechanical and welding test results for design of the large helical deviceA. Nishimura, H. Tamura, S. Imagawa, 7. Satow, S. Satoh, O. Motojima 873

High voltage regulator for power modulation of a gyrotron with voltagedepressed collectorG.A. Muller, W. Forster, V. Erckmann 877

Effects of the Eddy current flowing in the cold structures of the ITERmagnet systemR. Albanese, E. Coccorese, J.L. Duchateau, N. Mitchell, G. Reitano,G. Rubinacci, E. Zapretilina 879

Coil Designs for a Quasi-Axially Symmetric StellaratorM. Dreviak 883

Reactive Power Compensation for the Pulsed Power Supply of ASDEXUpgradeC. Sihler, B. Streibl, R. Klein, W. Schluter, M. Krohn 887

The HT-7U superconducting tokamak model coilsP.D. Weng, Y. Pan, S.T. Wu, Y.F. Bi, W.Y. Wu, B.Z. Li, B.Z. Chen, Y.H. Zhu,X. Wu, Y. Chao, J. Li, D. Wu, W.J. Pan, Q. Chen, D. Gao, J. Yu, W. Zhu,J. Wen, L.P. Cheng , Y. Tao 891

Concept and sensors for "extrinsic" diagnostic of superconductingmagnet systems from the safety point of viewM. Zhelamskij, N. Gorbachuk, A. Anghel 891

XXXV

Structural assessment of the ITER magnet systemC. Sborchia, A. Alekseev, A. Arneman, R. Gallix, M. Huguet, C. Jong,Y. Krivchenkov, A. Malkov, N. Mitchell, A. Panin, B. Stepanov, R.J. Thome,P. Titus, F. Wong 899

Stress analysis of the conductor and support structure for poloidal fieldcoils of SST-1 tokamakB. Biswas, V. Jain, K.J. Thomas, Y.C. Saxena 903

VOLUME 2

Section F : Fuel Technologies

Performances of an hybrid vacuum pump prototype at low temperatureJ.P. Perin, J. Manzagol, J.J. Cordier, P. Garin, F. Samaille 909

PILATUS : A Test Facility for Tritium Extraction from a Solid BreederBlanketE. Hutter, H. Albrecht, G. Neffe 913

Pellet injectors for a steady state fuellingI.V. Viniar, S. Sudo, A. Umov, S. Skoblikov, P.V. Reznitchenko 917

The experimental basis for the ITER cryopump regeneration conceptChr. Day, A. Mack, D. Murdoch, D. Rohrig 921

Dynamic compact mass-spectrometer for in-line mode analysis of ITERfuel mixture.Preliminary tritium testing & calibration experimentsG.L. Saksagansky, N.N. Aruev, I.L. Fedichkin, E.L. Koira, A.V. Kozlovsky,B.A. Mamyrin, S.N. Markovsky 925

Investigation of the Deuterium Release rate in the Electric PulsedHydride Injector (EPHI)Yu.A. Kareev, U. Tamm, I.S. Glushkov, E. Hutter, V.P. Novikov, R.-D. Penzhorn, V.V. Frunze 929

Getter bed for tritium handling : temperature evolution during loadingsequencesF Ghezzi 933

Tritium inventories of catalyst beds used in torus exhaust clean-upprocessesM. Glugla, R. Kraemer, 7.L Le, R.D. Penzhorn, K.H. Simon, J. Wendel 937

Development status of high speed pellet injectors for fusion devicesfuellingA Geraud, J.P. Perin, G. Gros 941