The equatorial visible/infrared Wide Angle Viewing System (WAVS) is one of the ITER key diagnostics for machine protection. It has to monitor the Plasma Facing Components (PFCs) by infrared thermography and visible imaging. Foreseen to be installed in 4 equatorial port plugs to maximize the coverage of divertor, first wall, heating antennas and upper strike zone, the WAVS is composed of 15 lines of sight and 15 optical systems transferring the light along several meters from the PFCs through the port plug and interspace up to the detectors located in the port cell. After a conceptual design phase led by ITER Organization, the design is being further developed through a Framework Partnership Agreement signed between the European Domestic Agency, Fusion for Energy, and a consortium gathering CEA, CIEMAT (with INTA as third party) and Bertin Technologies company. First the WAVS measurement specifications are presented. Secondly the description of the current design is given both for the in-vessel system and for the ex-vessel one. The on-going neutronic studies are depicted as well as the cameras and data acquisition system foreseen for the back-end of the diagnostic.

This paper presents the technical solutions and methodologies that are used and under development for managing the design lifecycle of the WEST project (W - for tungsten - Environment in Steady-state Tokamak, upgrade of Tore Supra's with actively cooled tungsten plasma facing components) fusion components and explains the interfaces that are implemented or in construction to connect together the different tools like documents management system, CAD modeler, or simulation codes around the data management backbone. It describes the methodologies used on the WEST project to optimize the design process by managing the engineering data workflow and ensuring the consistency between the different 3D representations for design or analysis as well as the specification or interfaces documents. Finally it explains how this platform contributes to reach the project targets in terms of performance, cost and schedule. (C) 2014 Elsevier B.V. All rights reserved.

In parallel to the direct contribution to the procurement phase of ITER and Broader Approach, CEA has initiated research & development programmes, accompanied by experiments together with a significant modelling effort, aimed at ensuring robust operation, plasma performance, as well as mitigating the risks of the procurement phase. This overview reports the latest progress in both fusion science and technology including many areas, namely the mitigation of superconducting magnet quenches, disruption-generated runaway electrons, edge-localized modes (ELMs), the development of imaging surveillance, and heating and current drive systems for steady-state operation. The WEST (W Environment for Steady-state Tokamaks) project, turning Tore Supra into an actively cooled W-divertor platform open to the ITER partners and industries, is presented.

Tore Supra routinely addresses the physics and technology of very long-duration plasma discharges, thus bringing precious information on critical issues of long pulse operation of ITER. A new ITER relevant lower hybrid current drive (LHCD) launcher has allowed coupling to the plasma a power level of 2.7 MW for 78 s, corresponding to a power density close to the design value foreseen for an ITER LHCD system. In accordance with the expectations, long distance (10 cm) power coupling has been obtained. Successive stationary states of the plasma current pro le have been controlled in real-time featuring (i) control of sawteeth with varying plasma parameters, (ii) obtaining and sustaining a 'hot core' plasma regime, (iii) recovery from a voluntarily triggered deleterious magnetohydrodynamic regime. The scrape-off layer (SOL) parameters and power deposition have been documented during L-mode ramp-up phase, a crucial point for ITER before the X-point formation. Disruption mitigation studies have been conducted with massive gas injection, evidencing the difference between He and Ar and the possible role of the q = 2 surface in limiting the gas penetration. ICRF assisted wall conditioning in the presence of magnetic eld has been investigated, culminating in the demonstration that this conditioning scheme allows one to recover normal operation after disruptions. The effect of the magnetic eld ripple on the intrinsic plasma rotation has been studied, showing the competition between turbulent transport processes and ripple toroidal friction. During dedicated dimensionless experiments, the effect of varying the collisionality on turbulence wavenumber spectra has been documented, giving new insight into the turbulence mechanism. Turbulence measurements have also allowed quantitatively comparing experimental results with predictions by 5D gyrokinetic codes: numerical results simultaneously match the magnitude of effective heat diffusivity, rms values of density uctuations and wavenumber spectra. A clear correlation between electron temperature gradient and impurity transport in the very core of the plasma has been observed, strongly suggesting the existence of a threshold above which transport is dominated by turbulent electron modes. Dynamics of edge turbulent uctuations has been studied by correlating data from fast imaging cameras and Langmuir probes, yielding a coherent picture of transport processes involved in the SOL.

In fusion devices, infrared (IR) imaging systems are used routinely for monitoring the surface temperature of plasma-facing components exposed to high heat fluxes in order to prevent and assess potential damages. For a better understanding of the experimental IR measurements, a realistic photonic simulation has been developed from a ray-tracing Monte Carlo code. This simulation has been performed on the IR diagnostic of the existing fusion device Tore Supra in Cadarache (France). First IR simulated images are presented. The similar features of the light between the simulation and experimental data are then emphasized.

R. Abgrall,1 M. H. Achard, J. Adam, G. Agarici, E. Agostini, M. Airaj, F. Albajar-Vinas, L. Allegretti, J. P. Allibert, J. C. Alliez, A. Allouche,2 J. Andreoletti, J. M. Ane, P. Angelino, T. Aniel, G. Antar, N. Arcis, A. Argouarch, C. Arnas,2 G. Arnoux, R. Arslanbekov, J. F. Artaud, E. Asp, S. Assas, G.Attuel, R.Aymar,A.Azeroual, S. Balme, O. Barana, B. Bareyt, V. Basiuk, M. Basko, P. Bayetti, L. Baylor,3 B. Beaumont, R. Becherer, A. Becoulet, M. Becoulet, L. Begrambekov,4 S. Benkadda,2 F. Benoit, V. Bergeaud, G. Berger-By, S. Berio, P. Bernascolle, N. Bernier, M. Berroukeche, B. Bertrand, D. Bessette, P. Beyer,2 P. Bibet, J. Bizzaro, P. Blanchard,5 J. Blum,6 S. Boddeker, D. Boilson,7 G. Bon Mardion, P. Bonnel, X. Bonnin, J. Boscary, G. Bosia, J. M. Bottereau, F. Bottiglioni, H. Bottollier-Curtet, C. Bouchand, G. Bouligand, F. Bouquey, C. Bourdelle, R. Bregeon, F. Bremond,8 S. Bremond, C. Breton, M. Breton, C. Brosset, R. Brugnetti, J. L. Bruneau, J. Bucalossi, R. V. Budny,9 Y. Buravand, C. Bush,3 M. N. Bussac,10 A. Cambe, H. Capes, J. J. Capitain, P. Cara, J. L. Carbonnier, S. Carpentier, J. Carrasco, A. Casati, O. Chaibi, C. Chamouard, M. Chantant, P. Chappuis, D. Chatain, E. Chatelier, M. Chatelier, J. H. Chatenet,10 X. P. Chen, L. Cherigier, G. Chevet, L. Chiarazzo, D. Ciazynski, G. Ciraolo, F. Cismondi, F. Clairet, J. Clary, C. Clement, L. Colas, N. Commaux, E. Corbel, J. J. Cordier, Y. Corre, L. Costanzo, A. Cote, J. P. Coulon, L. Courtois, X. Courtois, B. Couturier, J. P. Crenn, P. Cristofani, N. Crouseilles,11 O. Czarny, P. Da Silva Rosa, C. Darbos, G. Darmet, M. Davi, R. Daviot, H. De Esch, B. De Gentile, J. C. De Haas, E. De La Cal, C. De Michelis, C. Deck, J. Decker, P. Decool, P. Degond, R. Dejarnac, E. Delchambre, E. Delmas, L. Delpech, H. Demarthe, M. Dentan, G. Depret, P. Deschamps, C. Desgranges, P. Devynck, L. Doceul, N. Dolgetta, C. Doloc, Y. Dong,12 P. Dore, D. Douai, H. Dougnac, H. W. Drawin, J. Druaux, M. Druetta,13 F. Dubois, M. Dubois, N. Dubuit, J. L. Duchateau, T. Dudok de Wit, E. Dufour, R. Dumont, G. Dunand, L. Dupas, Y. Duran,14 A. Durocher, D. Edery, A. Ekedahl, D. Elbeze, L. G. Eriksson, D. Escande,2 A. Escarguel, F. Escourbiac, T. Evans,15, F. Faisse, G. Falchetto, T. Fall, M. Farge,16 J. L. Farjon, E. Faudot,17 P. Fazilleau, N. Fedorczak, C. Fenzi-Bonizec, J. R. Ferron,15 I. Fidone, C. Figarella, E. Fleurence, I. Fleury, M. Fois, C. Forrest,15 C. A. Foster,3 S. Fouquet, C. Fourment, D. Fraboulet, P. Francois, B. Franel, D. Frigione,18 P. Froissard, G. Fubiani, V. Fuchs,14 M. Fumelli, B. Gagey, V. Galindo, D. Gambier, L. Garampon, X. Garbet, R. Garbil, J. Garcia, J. L. Gardarein, L. Gargiulo, P. Garibaldi, P. Garin, E. Gauthier, A. Geraud, T. Gerbaud, F. Gervais,19 M. Geynet, P. Ghendrih, T. Gianakon, R. Giannella, C. Gil, J. P. Girard, G. Giruzzi, L. Godbert-Mouret,2 P. Gomez, M. Goniche, A. Gordeev,4 G. Granata, V. Grandgirard, R. Gravier, B. Gravil, M. Gregoire, S. Gregoire, P. Grelot, D. Gresillon,19 C. Grisolia, G. Gros, *Other affiliations are those at the time the collaborations began. 1INRIA-CNRS, Université Sciences et Technologies, Bordeaux, France 2Physique des Interactions Ioniques et Moléculaires ~PIIM !, Université de Provence, Centre Universitaire St Jérôme, 13397 Marseille Cedex 20, France 3Oak Ridge National Laboratory, Fusion Energy Division, P.O. Box 2009, Oak Ridge, Tennessee 37831-8070, USA 4Moscow Physics and Engineering Institute ~MEPhI!, 31 Karhirskoe Sh, 115409 Moscow, Russian Federation 5Centre de Recherche en Physique des Plasmas, Association EURATOM-Confédération Suisse, Ecole Polytechnique Fédérale, PPB-Ecublens, 1015 Lausanne, Suisse 6Université Joseph Fourier, Grenoble I, B.P. 53, 38041 Grenoble Cedex 9, France 7School of Physical Sciences, Dublin City University, Glasnevin, EI-Dublin 9, Ireland 8INRIA Sophia-Antipolis, 2004 Route des Lucioles, B.P. 93, 06902 Nice-Sophia-Antipolis, France 9Princeton Plasma Physics Laboratory, James Forrestal Campus, Princeton, New Jersey 08543, USA 10Centre de Physique Théorique, Ecole Polytechnique, 91128 Palaiseau, France 11IRMA, Université Louis Pasteur, Strasbourg, France 12Southwestern Institute of Physics, Chengdu 610041, China 13Laboratoire TSI, Université Jean Monnet, 42023 St-Etienne, France 14Association EURATOM-IPP.CR, Institute of Plasma Physics AS CR, Za Slovankou 3, 182 21 Praha 8, Czech Republic 15General Atomics, P.O. Box 85608, San Diego, California 921865608, USA 16LMD, Ecole Normale Supérieure, 75 Paris, France 17LPMIA, Université Henri Poincaré, Nancy 1, B.P. 239, 54506 Vandœuvre Cedex, France 18Associazione EURATOM-ENEAsulla Fusione, C.R. Frascati, Roma, Italy 19Laboratoire de Physique et Technologie des Plasmas ~LPTP!, Ecole Polytechnique, 91128 Palaiseau, France

The main results of the Tore Supra experimental programme in the years 2007–2008 are reported. They document significant progress achieved in the domain of steady-state tokamak research, as well as in more general issues relevant for ITER and for fusion physics research. Three areas are covered: ITER relevant technology developments and tests in a real machine environment, tokamak operational issues for high power and long pulses, and fusion plasma physics. Results presented in this paper include test and validation of a new, load-resilient concept of ion cycotron resonance heating antenna and of an inspection robot operated under ultra-high vacuum and high temperature conditions; an extensive experimental campaign (5 h of plasma) aiming at deuterium inventory and carbon migration studies; real-time control of sawteeth by electron cyclotron current drive in the presence of fast ion tails; ECRH-assisted plasma start-up studies; dimensionless scalings of transport and turbulence; transport experiments using active perturbation methods; resistive and fast-particle driven MHD studies. The potential role of Tore Supra in the worldwide fusion programme before the start of ITER operation is also discussed.