Activity Report

Transcription

1 CONSIGLIO NAZIONALE DELLE RICERCHE Dipartimento Energia e Trasporti Activity Report Istituto di Fisica del Plasma Piero Caldirola Associazione EURATOM-ENEA-CNR Via R. Cozzi Milano Italy

2 Edited by Augusta Airoldi 2 IFP Activity Report

3 Foreword / Prefazione Negli ultimi due anni l importanza su scala mondiale della ricerca in Fisica del Plasma ha ripreso a crescere significativamente, in larga misura come conseguenza della storica decisione di avviare il Progetto ITER per un prototipo di reattore a fusione termonucleare. La complessità dell impegno organizzativo di questa impresa, centrata sull esperimento da realizzarsi in Provenza nei prossimi decenni, pone nuove sfide e richiede precisi orientamenti programmatici degli istituti di ricerca nazionali. Solo questo infatti potrà permettere loro di avere un ruolo scientifico importante e fornire un sostegno di alte competenze al sistema produttivo nazionale. Allo stesso tempo va salvaguardata l indipendenza di giudizio e di scelta scientifica degli Istituti, essendo questa la sola garanzia di progresso e di capacità innovativa della ricerca, che non può essere ridotta ad un servizio finalizzato. In questo contesto l IFP ha sviluppato al suo interno risorse umane e scientifiche che lo mettono in grado di competere e collaborare con importanti Enti di ricerca nel settore della fisica del plasma e della fusione nucleare in Europa, mantenendo sia alte competenze disciplinari che la capacità di eseguire ricerca finalizzata sotto contratti attivi. Questa capacità di sostenere gli impegni richiede soprattutto un periodo di certezze organizzative all interno del CNR e nell ambito del contratto Euratom afferente al VII programma Quadro della Comunità europea. Il settore di elezione della ricerca svolta da IFP è da molti anni quello della fisica dell interazione di onde elettromagnetiche con i plasmi di laboratorio, con particolare riguardo alle sue applicazioni al confinamento magnetico. Attualmente IFP/CNR partecipa come Unità di Ricerca Euratom al programma di ricerca sulla Fusione Termonucleare previsto nel VII Programma Quadro della Unione Europea, nell ambito del Contratto FUAI-I di Associazione Euratom-ENEA e del 14.mo Atto Aggiuntivo del Contratto ENEA- CNR. Ancora per il 2007 questo contratto coprirà forfettariamente il costo pieno del personale dell Unità di Ricerca ed i costi di investimento e funzionamento al 20% relativi al programma approvato dal Comitato di Gestione Euratom. Il più rilevante impegno assunto dall IFP continua ad essere lo sviluppo e conduzione degli impianti e degli esperimenti di riscaldamento del plasma nel tokamak FTU del CRE-ENEA mediante assorbimento risonante di onde millimetriche (ECRH), per una potenza complessiva di 1,6 MW. Gli obiettivi del biennio ed i risultati raggiunti hanno permesso di acquisire visibilità internazionale sull importante tema del controllo automatico mediante ECRH delle instabilità magnetoidrodinamiche (MHD), che costituiscono uno dei più seri problemi dei tokamak, e sull altrettanto importante problema della realizzazione di avanzate diagnostiche elettromagnetiche per misure di temperatura elettronica e ionica. Sul tokamak FTU si sono ottenuti anche importanti risultati sulla tecnica di diagnosi della temperatura ionica basata sullo scattering collettivo. Nel biennio l IFP ha operato nell ambito di numerosi contratti finalizzati alla progettazione di componenti di ITER ed ha partecipato attivamente alla gestione scientifica dell esperimento comunitario JET inviando personale con ruolo chiave per la gestione sia di Task Forces che di esperimenti. Associati a questi temi di fisica sperimentale di alto livello, l IFP ha sviluppato ed approfondito ricerche teoriche sulla propagazione e l assorbimento risonante di fasci Gaussiani di onde ciclotroniche elettroniche, e sull associata generazione non induttiva di corrente, producendo anche un codice numerico che attualmente è riconosciuto internazionalmente come il più avanzato. Grazie al lavoro di pianificazione e di conduzione di esperimenti al JET da parte del personale IFP e all analisi ed interpretazione dei risultati relativi, si è costruito un quadro coerente dei fenomeni di trasporto di energia e di momento nei principali scenari di operazione del tokamak. Si sono sviluppati modelli fluidi generali di plasmi multispecie collisionali ed esplorati gli effetti della rotazione non uniforme del plasma sulle instabilità reattive non collisionali che sono considerate tra le cause più importanti del regime turbolento di trasporto di energia in un burning plasma. Un significativo lavoro teorico è stato svolto anche nell ambito dei modelli fisici nonlineari delle instabilità resistive neoclassiche e dei meccanismi di stabilizzazione. Nel biennio considerato IFP Activity Report

4 in questo rapporto l IFP ha anche realizzato, installato e provato un nuovo apparato di misura della radiazione ECE al JET, corredandolo dei codici numerici di interpretazione degli spettri misurati. E proseguito lo sviluppo di ricadute tecnologiche nel settore di apparecchiature ausiliarie per misure di propagazione e assorbimento di microonde e di processi al plasma per il trattamento superficiale di materiali, inorganici ed organici, con registrazione di alcuni brevetti e coinvolgimento di piccole industrie specializzate. In particolare recentemente si sono sviluppate applicazioni avanzate di tecnologie al plasma nella realizzazione di polimeri semiconduttori. Per esprimere tutte le sue positive potenzialità, sviluppando le competenze di fisica del plasma orientate al progetto fusione, e cooperare utilmente con gli altri Istituti ed Enti Italiani e stranieri, nel 2006 l IFP ha iniziato il rinnovamento ed adeguamento del proprio laboratorio nella sede di Milano, basandosi interamente su un impiego razionalizzato di risorse proprie e di una concessione in comodato di materiale del CRPP di Losanna. L esperimento basato su un plasma multispecie confinato in cuspide magnetica è in fase di conclusione. Esso sarà sostituito da un nuovo apparato strumentale (GyM) consistente in una macchina lineare, attualmente in corso di allestimento, progettata per studiare in scala ridotta, secondo rigorosi criteri di similarità fisica, diversi problemi di interesse fusionistico ed applicazioni tecnologiche. Un elemento qualificante dell impianto è la sorgente a radiofrequenza costituita da un Gyrotron GYCOM da 28 GHz a 15 kw, e la possibilità di avere plasmi completamente ionizzati in regime non collisionale (a bassa temperatura e densità) facilmente diagnosticabili con sistemi di acquisizione dati moderni e automatizzati. Interessanti collaborazioni internazionali, con scambi di strumenti e personale scientifico sosterranno la realizzazione e sperimentazione. Diverse attività su contratti EFDA sono prevedibili, a partire dal 2008, su problemi delle instabilità nel divertore di un tokamak e della turbolenza ITG. Con una strumentazione adeguata e moderna con la giusta flessibilità per condurre studi di fisica del plasma che sarebbe troppo oneroso fare in grandi laboratori, l IFP, pur rimanendo un centro di ricerca di piccole dimensioni, può presentarsi nel contesto internazionale in modo attraente per collaborazioni scientifiche di valore per parecchi anni. L IFP svolge una costante azione formativa al livello di lauree e dottorati di ricerca in Fisica ed Ingegneria, con studenti e candidati di università italiane e straniere e sarà presto sede di una Borsa di Addestramento Europea EFTS, contribuendo in modo rilevante allo sviluppo delle competenze italiane nel settore fusione. Stabili rapporti culturali e operativi sono definiti con le Università degli Studi di Milano, l Università di Milano-Bicocca, il Politecnico di Milano, le Università di Padova, Pisa, Torino, Napoli Federico II, IST-CFN di Lisbona, Ecole Polytechnique Federale de Lausanne, Chalmers University of Technology di Goeteborg, Università di Uppsala, IAP dell Accademia delle Scienze Russa di Nizhny Novgorod, IPP Max-Planck, favorendo l integrazione dei gruppi universitari nei grossi progetti della fusione europea. La pluriennale esperienza e tradizione di competenze dell'ifp nella teoria della fisica del plasma e in particolare dell'interazione onde-plasma è uno dei punti di forza dell'istituto, riconosciuto internazionalmente. Queste competenze permettono di affrontare problemi di avanguardia e di acquisire numerosi contratti di ricerca e studio, mantenendo alto il livello di addestramento anche del personale più giovane e qualificando professionisti in grado di inserirsi con molto successo nei centri di ricerca internazionali. I piani di sviluppo scientifico e tecnico dell attività IFP proseguiranno, nell ambito delle iniziative europee e nazionali, in un quadro organizzativo per obiettivi, che portino a risultati verificabili, con uno sforzo naturalmente commisurato alla risorse umane e materiali disponibili. Il Direttore Enzo Lazzaro 4 IFP Activity Report

5 Contents I General information 7 II Collaborations 9 1. Experiments and modeling in toroidal fusion plasmas 1.1 ECH-LHCD synergy and disruption mitigation in FTU Collective Thomson Scattering on FTU Core transport studies in JET Transport studies in ASDEX Upgrade Control system of magnetic islands Development and operation of ECE oblique diagnostics on JET Neutron spectrometery instruments and measurements on JET Gamma spectroscopy diagnostics for JET Theoretical research in plasma physics 2.1 Gaussian beam propagation, absorption and current drive generation Interpretative ECE emission code Magnetohydrodynamic equations for multicomponent plasmas Critical island width for NTM modes Effects of sheared rotation on ITG modes stability Microislands and transport in tokamaks Electron holes in a non-uniform collisionless plasma Ultraintense electromagnetic radiation in plasmas ITER relevant studies 3.1 Capabilities of ECRH/ECCD system in ITER Studies for the ITER ECRH/ECCD system Development of innovative microwave Diplexer/Combiner Contribution to ITER reflectometry diagnostics Plasma microtorch for ITER wall diagnostic Microwave applications and instrumental facilities for wave plasma physics 4.1 Testing of the Flight Model-Flight Spares components for Planck-LFI instrument A cusp plasma device for plasma studies and technological applications Measurements of fluctuations spectra in a Carbon dusty plasma Methane cracking and hydrogen production in Ar plasma at atmospheric pressure Planning and objectives of a flexible plasma facility for scaled plasma experiments (GyM) Plasma-aided material processing 5.1 Plasma production of semiconducting and conducting polymers Plasma treatment of biodeteriorated ancient papers Plasma treatment of Polymeric Composite Materials for Industrial application (patent No.: MI2006A002482) Surface analysis of plasma exposed tokamak tiles (ERCAR task) Highly absorptive ceramic coatings for high power microwaves in the mm-waves range (patent No.: PCT/EP2006/050605) 49 IFP Activity Report

6 6. Patents European Contracts Industrial Contracts Publications Refereed Publications 55 Conference Proceedings 61 Conference Presentations 66 Scientific and technical reports 69 Books Acronym List 71 6 IFP Activity Report

7 General information In the frame of the organization of Italian Consiglio Nazionale delle Ricerche (CNR) the Istituto di Fisica del Plasma Piero Caldirola (IFP) is part of the Dipartimento Energia e Trasporti of CNR, and has an internal matrix structure along three functional lines ( commesse ) coordinated within the department project: Participation to international thermonuclear Fusion research. The mission of the Institute, grown in thirty years of activity performed in close contact with international institutions and within the Euratom research framework, is scientific and technological research in the field of laboratory plasma physics, with particular focus on the interaction of electromagnetic waves with plasmas. The institute is also a member of the Euratom-ENEA CNR Association and the Director of IFP and Head of the EURATOM Research Group in Milano is Dr. Enzo Lazzaro. The IFP professional staff amounts to 19 Permanent CNR members, 9 temporary contractors and research fellows, 5 external collaborators. The support staff includes 9 technicians, 5 administrative and secretarial personnel. Detailed information on the Institute may be obtained via web at: IFP Activity Report

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9 II Collaborations International Institutions EFDA-ITER, Garching (D) EFDA-JET, Abingdon (UK) Max-Planck Institut für Plasmaphysik, Garching (D) Max-Planck Institut für Plasmaphysik, Greifswald (D) University of Technology Darmstadt, Darmstadt (D) DRFC CEA-Association EURATOM-CEA sur la Fusion, Cadarache (F) Conseil National de Recherche Scientifique, CNRS (F) CELIA-CNRS, Université Bordeaux 1 (F) FOM Instituut voor Plasmaphysica, Rijnhuizen (NL) CFN-Instituto Superior Tecnico, Lisboa (P) CRPP-EPFL, Losanna (CH) Uppsala University (S) Chalmers University of Technology (S) INTAS Project, Brussels (B) Institute of Plasma Physics, Czech Academy of Sciences, Prague (CZ) Istituto di Fisica Generale, Russian Academy of Sciences, Mosca(CSI) Istituto di Fisica Applicata (IAP), Russian Academy of Sciences, Nizhny Novgorod (CSI) Istituto di Fisica Nucleare "Budker", Russian Academy of Sciences, Novosibirsk (CSI) Istituto di Fisica, Georgian Academy of Sciences, Tbilisi (Georgia) MIT, Cambridge (USA) LLNL, Livermore (USA) General Atomics, Livermore (USA) University of Saskatchewan, Saskatoon, Canada National Institute for Fusion Science (J) JAEA, Advanced Photon Research Center, Kizu, Kyoto, (J) National Institutions ASI - Roma CINECA-Bologna CRE-ENEA, Frascati CRE-ENEA, Bologna CNR-IASF Bologna e Milano CNR-IENI, Milano Consorzio RFX, Padova Università di Napoli "Federico II" Dip. Scienze Fisiche, Monte Sant'Angelo Università di Milano Università di Milano-Bicocca Politecnico di Milano Università di Pisa IFP Activity Report

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11 1. Experiments and modeling in toroidal fusion plasmas 1.1 ECH-LHCD synergy and disruption mitigation in FTU ECH-LHCD synergy One of the motivations of the ECRH project on FTU was to study suprathermal absorption of EC waves by the fast electrons sustained by LHCD, this being a promising mechanism for a quantitative non-inductive current drive in tokamak. Suprathermal absorption is based on an up/down shift of the EC frequency due to a combination of a Doppler effect, in case of toroidal injection of the wave, and a relativistic effect shift due to the speed of the fast electron tail. The wave is absorbed directly by the fast electrons increasing their parallel momentum and creating a net term of current drive with an efficiency larger than in the usual bulk ECCD. On FTU the down-shift (B T >B res ) absorption regimes has been widely studied and exploited in synergy experiments with LHCD carried out with a central B T =7T, plasma current in the kA range and average electron density in the m -3 range. Up to 1.2MW of EC power in O-mode have been injected in a plasma where partial current drive was achieved injecting 1MW (or more) of LH power. The EC toroidal angle was varied from 30 to +20, while the LH power was injected at n // =1.58. The cold resonance was outside the plasma column. The overall absorbed power fraction varied in the range 50-80% depending on the LHCD power and the electron density. In order to compare the synergetic effects with the results obtained by LH alone, we used the CD efficiency: η cd = I R n cd e (P LH + P EC ) (Z eff + 5) 6 with R the major radius, n e the average line density, P LH and P EC the injected LH and EC power, respectively. The last term at the r.h.s of the formula above renormalizes the data at the ideal case with Z eff =1. The synergy efficiency, calculated considering the whole injected power, is comparable with that of LH alone and two order of magnitude higher than the one obtained with bulk ECCD, as shown in Fig η cd (10 20 A W -1 m -2 ) LHCD LHCD+EC ECCD measured ECCD calculated Fig Comparison of the CD efficiency for LHCD (squares), synergetic LHCD+EC (circles) and ECCD (diamonds from calculation and triangles from measurements). The abscissa is the volume averaged electron temperature <Te> Disruption mitigation A most important issue for ITER operation is the avoidance of disruptions. Besides a fast system acting on the currents of the coils controlling the plasma position, independent IFP Activity Report

12 systems (e.g., fast gas injectors) are presently under investigation to reduce or mitigate disruptions. As ECRH power has been demonstrated to affect the evolution of the MHD activity, the driving mechanism of most disruptions, experiments have been carried out focused on controlling the evolution of disruptions by ECRH. Disruptions have been triggered in FTU by impurity injection using both the Laser Blow Off (LBO) technique and gas puffing to bring the plasma density above the Greenwald limit. The ECRH power has been triggered based on a threshold in the loop voltage, which always increases before a disruption. The experiments have been carried out using up to 3 gyrotrons (1.2 MW) and injecting the EC power, both on-axis or off-axis, in the O-mode and in perpendicular direction. Disruptions due to the density limit (n e = m -3, I p =360kA, B T =5.3T), were avoided injecting 0.8MW of ECRH power at r dep =0, after the start of MHD activity. In the case of disruptions triggered injecting metallic impurities (molybdenum on n e = m -3, I P =500kA, B T =5.3T plasma), instead, disruption avoidance, or retardation, was obtained with off-axis heating Δt D (s) Δt ECRH <100 ms Fig Disruption duration vs power deposition radius (from the ECWGB code) ρ dep Fig.1.1.2, where Δt D is plotted versus ρ dep, shows the difference between the time at which I p reaches a nearly zero level and the time at which the mode starts growing. The soft x-ray data and beam tracing calculations further show that disruption avoidance is obtained only when the power is absorbed near to the position of the m=2 island. 1.2 Collective Thomson Scattering on FTU Of special relevance among the several ITER-oriented experimental activities of FTU is the diagnostic experiment of mm-wave collective Thomson scattering (CTS) due to its being performed in the propagation window below the EC resonance, f gyr <f EC, presently proposed for ITER. A recent feasibility study clearly stated that the CTS diagnostic of the fast ions, including the fusion-born alphas, in ITER will require propagation in the X mode at f gyr =50-60GHz, to be compared with f EC0,ITER =151GHz (B T0,ITER =5.4T). Being related to the magnetic field, the possibility of performing CTS in these conditions is peculiar to a high field device as FTU. The probing radiation is provided by a gyrotron at f gyr =140GHz, shared with ECRH applications. The experiment has been run at 7T<B T0 <8T, corresponding to 196GHz<f EC <224GHz. Interesting results were obtained following the unambiguous interpretation of strongly anomalous non-thermal spectra systematically observed both in aligned and misaligned antenna conditions and finally explained at the conclusion of a dedicated experimental campaign carried out in The results being extensively reported in a dedicated paper, here we limit ourselves to summarize the main of them. 12 IFP Activity Report

13 Fig Schematic view of the geometry of one of the two multimirror quasi-optical antennas of CTS in FTU Fig schematically shows one of the two multi-mirror quasi-optical antennas we used in CTS on FTU. The gyrotron beam is injected from the top and the scattered beam is collected from the bottom of the same port. To avoid modulations at the fast magnetosonic frequency in the spectra, the scattering plane is tilted by about 10 with respect to the poloidal plane. The propagation conditions are such that the polarization of the two plasma modes is sensibly elliptical. In the experimentation the scattering volume was normally placed on the vessel axis. The several modifications implemented in the receiving system and in the operational procedures to profitably investigate the anomalous spectra, a typical example of which is shown in Fig , are described in a dedicated paper to be published S [kev] Δt=+85ms Fig Typical anomalous spectrum f [GHz] While significantly varying from shot to shot, the spectral power densities of the anomalous spectra are several orders-of-magnitude higher than those predicted for the ion-thermal feature (=0.5keV). Moreover, at its origin the spurious signal underlying these spectra is even stronger since it is collected after multiple reflections at the vessel wall and therefore subject to antenna decoupling, of the order of 50dB. Only a few spectral lines were present in a single spectrum. The line frequencies were verified to be recurrent statistically. Attempts of explaining the spectra in terms of plasmawave processes soon failed. Among the several tests performed to investigate the origin of these spectra, of special significance in definitely confirming their nature of perturbed gyrotron spectra were tests carried out with the signal picked-up directly from the high-power transmission line, hence before the probe beam entered the plasma. Indeed, these tests revealed that the spectra were produced even in the absence of plasma only, provided a toroidal magnetic field was applied. This evidence led us to investigate the possible effects of resonances and cut-offs in causing a back-reflection of the beam power. In the CTS configuration with f gyr <f EC an EC layer, an upper hybrid layer, and the right-handed cut-off for the extraordinary (X) mode are unavoidably crossed by the probe beam when propagating in the injection port. In these conditions, whenever a mode mixture is injected as it was our IFP Activity Report

14 case, the power fraction in the X mode is partially reflected at the cut-off layer, provided a breakdown plasma converting the critical layers from latent to active is excited by the beam itself. A reconstruction of the isolines of the magnetic field in the beam injection port further showed that the EC layer was located just near the port mouth (see Fig.1.2.3). Evidence was achieved that the critical layers crossed the last two mirror surfaces. While slightly displaced outwards, the other two critical layers fall close to the EC layer. A final confirmation of the interpretation given above was obtained at the end of the experimental campaign, where antenna inspection showed that wakes were present on the surfaces of the last two mirrors at a location and with an inclination exactly corresponding to the resonant (B=fgyr/28=5T) isolines for the axial magnetic fields most frequently used in the experimentation (BT0=7.2T and 8T). Fig Isolines of the magnetic field in the FTU port. The position of the final antenna mirror is also shown. Peculiarities of the layout, e.g., the high power density consequent to the necessity of containing the beam size in the port due to spatial limitations typical of a cryogenic devices, may have contributed to strengthen the gyrotron perturbation in our specific case. Nevertheless the risk for this perturbation to occur in CTS experiments with f gyr<fec can be considered quite general. Transmitting antennas such as to make the critical layers remain latent independently of the propagation conditions and of the power levels involved are therefore better adopted in these experiments. Also considering the MW power level at which the future CTS diagnostic will be operated, the constraints on the transmitting antenna indicated by our results, and the positive indications on how to overcome them they suggest, quite straightforwardly extend to the design of mm-wave CTS for ITER. 1.3 Core transport studies in JET IFP-CNR has played an active role in the coordination of transport studies in JET through the leadership of the JET Task Force Transport (TFT) by P.Mantica. In particular, the following topics have been addressed within TFT during with direct involvement of IFP-CNR: Core heat transport: electron and ion stiffness in L-mode, H-mode and hybrid plasmas has been investigated by means of electron temperature and, for the first time, ion temperature modulation. Experimental findings are consistent with the picture of anomalous transport driven by electrostatic instabilities (ITG-TEM) with a threshold in inverse temperature gradient length. Experimental values of thresholds are in the right ball-park of theory predictions, but detailed quantitative comparison of parametric dependences is on-going. JET plasmas are generally very stiff in both electron and ion channels, with stiffness level increasing with temperature, which extrapolates to very stiff behaviour and temperature profiles strongly determined by thresholds in ITER. 14 IFP Activity Report

15 Internal transport barriers (ITBs): although toroidal rotation driven by NBI is an important component in sustaining a fully formed ITB, the ITB triggering mechanisms are still not completely clear, with two main factors possibly playing a role, i.e. the negative magnetic shear and alpha stabilization effect, and the ExB shear due to an anomalous poloidal velocity. Experimentally ITB at JET are strongly triggered by proximity of the minimum q to a low order rational value. In addition, new measurements have indicated the presence of very large values of poloidal velocity during ITB phases, much larger than predicted by neoclassical theory. From Alfven cascades measurements it is clear that ITBs are formed slightly before q min reaches the rational value. The cause-effect relation between the onset of poloidal rotation and ITB triggering is under study. Electron and ion temperature modulation experiments in ITBs have also been performed, showing that ITBs are layers where the plasma is below the critical threshold for turbulence onset (see Fig.1.3.1). The heat wave behaviour when approaching and crossing the ITB has peculiar signatures fully consistent with the critical gradient picture. Fig.1.3.1: Left side) Experimental profiles at t=5.5 s of T e, T i, n e and q for shot (3.25T/2.6 MA, 3 He~20%, ICRH f=37 MHz). The ITB region is highlighted. Right side) profiles of Fourier component of amplitudes A (red squares) and phases ϕ (blue circles) at the modulation frequency (20 Hz) during the time interval s. Estimated RF power deposition profiles are also plotted (dashed black line). The strong damping of amplitudes and increase of phases in the ITB layer indicates that ITBs are narrow regions below threshold. Particle transport: further investigation of the increase in density peaking at low collisionality in H-mode plasmas has led to merging of JET and AUG database and to the prediction of a density peaking n e (ρ pol =0.2)/<n e > vol ~1.5 for ITER. Core particle sources are important, but not dominant, the main player for density peaking being an anomalous inward pinch. The peaking does not seem to depend on magnetic shear nor on temperature peaking, which is at variance with expectations from common models of turbulence-driven particle pinches such as the curvature pinch and thermodiffusion. Impurity transport: impurity transport in JET plasmas at low collisionality is dominated by anomalous turbulence-driven transport. Impurity pinches arise due to thermodiffusion, curvature and parallel velocity compressibility. Detailed studies using the linear gyrokinetic code GS2 indicate that the impurity peaking is a weak function of the impurity charge, unlike in neoclassical transport. This insensitivity of peaking to the impurity charge has been confirmed experimentally by injecting He, Ar, Ne and Ni and determining the diffusion and convection terms for each species. It has also been found that the use of RF as electron heating source is effective in eliminating impurity accumulation with respect to plasmas with no RF or RF in the ion heating scheme. The IFP Activity Report

16 effect takes place through a reversal of the convective velocity, and is attributed to the parallel compressibility pinch, which switches from inward to outward when the dominant instability changes from Ion Temperature Gradient Modes to Trapped Electron Modes. Momentum transport: a vigorous effort has been devoted to the investigation of both toroidal and poloidal momentum transport in JET. It was found that the ratio of the toroidal momentum to the ion heat diffusivity χ ϕ /χ i is well below 1, which is the standard assumption used for ITER predictions. Models like Weiland or GLF23 seem to reproduce the JET results reasonably well. An anomalously high value of the poloidal velocity with respect to its neoclassical values has been measured in JET in plasmas with ITBs. Theoretical investigation has led to suggest that such poloidal flow is generated by turbulence via terms like the Reynolds and Maxwell stresses. Comparison with the experimental data is presently under way and seems quite promising. A crucial issue that remains to be clarified is that whether the anomalous poloidal velocity is either the cause or a consequence of ITB formation. 1.4 Transport studies in ASDEX Upgrade Experiments in H-mode plasmas have shown that both heat and particle transport are sensitive to the ratio of the electron and the ion temperatures, T e /T i. While decreasing T e /T i is beneficial for confinement, increasing the electron heating in these plasmas deteriorates the confinement. H-mode plasmas with low T e /T i are often accompanied by a high toroidal rotation velocity v φ. Its gradient can destabilize the ion temperature gradient mode (ITG) through its parallel component in the parallel-velocity shear. It also has stabilizing effects since it produces an ExB shearing rate (ω ExB ). The correlation on T e /T i and v φ has been studied and compared with calculations made with the gyro-landau-fluid model GLF23 and the gyrokinetc code GS2. Experimentally it is shown that the normalized-gradient length of the ions (R/L Ti ) is correlated with both T e /T i and v φ. Peaked ion temperature profiles are obtained only with low T e /T i and high v φ, and vice-versa. The changes in T e /T i act directly on the ITG threshold, while the ones in v φ modify the ω ExB shearing rate, leading to changes in the effective threshold. 1.5 Control system of magnetic islands A crucial problem of present research in thermonuclear plasma physics in tokamaks is the control of rotating helical magnetic perturbations, associated with local distortions of the current density profile. These unstable perturbations can seriously degrade plasma and energy confinement and hamper the reliability of operation of the device. Control or total suppression is possible by restoring the current profile by means of localized injection of RF power. However the control problem requires a real-time experimental identification of the radial location of the rotating magnetic islands growing on tokamak isobaric magnetic surfaces where the field line pitch is a rational number q=m/n. Magnetic islands in a tokamak cause localized partial flattening of the plasma temperature (and pressure) profile that can be detected by radiative signals in the microwave band as Electron Cyclotron Emission (ECE) using a multichannel polychromator or radiometer tuned to frequencies corresponding to different radii R in the tokamak meridian cross-section. The typical signal can be considered as the superposition of an average component related to the equilibrium electron temperature, that to leading order is a flux function T 0 = T e (Ψ 0,t), and a sum of noise and coherent fluctuations due for instance to the magnetic perturbations that produce rotating 16 IFP Activity Report

17 islands in the nested magnetic surface geometry so that, in r/r<<1, the magnetic flux function is represented by r,ϑ,rφ coordinates and for Ψ = Ψ 0 ( r ) + ψ m,n (t) cos(mϑ nφ Δϕ (t)). The temperature fluctuation, δt e = T e (Ψ) T 0, is determined by the heat transport process across a finite size island. The fluctuation amplitude should be δt e 0 on the island centre, r s, and at the X stagnation point, which is the main information on island localization provided by the amplitude of T e oscillations. The relative phase of two neighbouring ECE channels changes smoothly except if a rational surface q=m/n, with a temperature-flattening island is located between them, so that a phase jump close to Δϕ = π occurs. A procedure applicable to a real time processing of the signals, looking at these features has been conceived. Considering pairs of normalised oscillating ECE signals from the i-th and j-th norm norm channel a correlation indicator between pairs of neighbouring channels P ij = o i o j is τ constructed with an average over a suitable time interval. A positive value P ij =1 means that a coherent oscillation is present, and a negative value P ij = 1 that a phase jump Δϕ = π occurs. Since at the island position the sequence P ij should occur, the localization algorithm looks for a minimum-well, or positive concavity, in the P ij sequence. The correlation principle between neighbouring ECE signals can be applied also to detect the radius of radiofrequency power absorption. Fig Block diagram of system for detection and control of magnetic islands The method is based on modulating in time, at a selected frequency the gyrotron pulse and finding the maximum correlation Q ig = o i normg between the normalized gyrotron power deposition ping and the associated temperature fluctuation o norm i = o i /A j, detected by the ECE diagnostics. Here g =1 if power is on or g = 1 if it is off. When no island is identified and power should be off, the power is periodically switched on with a 10% duty cycle, whereas when an island is recognized and the gyrotron should be switched on, it is modulated with 90% duty cycle. This allows detecting r dep as an observable. Therefore an array of gyrotron tuned for absorption at different radii is modulated at different frequencies and the correlation of pairs of ECE channels is monitored at the various modulation frequencies, permitting the identification of the location of the absorption layer. The novel detection/control principle we adopt is to use as error variable ε fb = r island r dep in a just align τ IFP Activity Report

18 strategy that allows a conscious search and possibility of parallel steering of multiple beams, by a variety of means. A real-time algorithm for the identification of the mode location and ECW power deposition has been designed and implemented on a purpose-built detection/control device installed on the FTU tokamak. The first prototype of an automatic, real-time detection/feedback control device, based on an original principle of mode identification and RF beam control has been developed (see Fig.1.5.1) and successfully tested in a closed-loop bang-bang (on-off) feedback experiment on the FTU tokamak. The system provides also experimental real-time information on the location of rational q surfaces, as shown in Fig Shot 27714: Correlation Pij ECE Channels plasma axis Fig Contour plot of the Pij function for FTU shot A minimum of correlation is found between channels 9 and 10 (grey track) that identifies the radial position of the magnetic island (and q=2 surface) t [sec] 1.6 Development and operation of ECE oblique diagnostic on JET Introduction The main interest of oblique ECE diagnostics resides in their providing information on the LHCD-induced high energy tails in the electron distribution function. To achieve this goal, an oblique ECE system was designed with the line of sight at large angle with respect to the perpendicular to the toroidal magnetic field, as required to gain sensitivity for the emission from high energy electrons. There are indications that the electron velocity distribution can be significantly non Maxwellian even at 1-3 times the thermal velocity. Since the angular distribution of the ECE radiation depends on the resonant energy of the emitting electrons, multiple angles of sight provide a scan of the electron distribution in the momentum space. This motivated the development of the oblique ECE diagnostic at JET. The physics data provided by oblique ECE will become even more valuable in the perspective of burning plasma experiments, since there high energy particles are expected to be present in a significant fraction. In order to make oblique ECE measurements possible at JET several upgrades have been introduced in the hardware, including a new antenna, a pair of smooth circular waveguides, part of the so-called Microwave Access of JET (MWA), and complete redesign of the existing single channel Fourier Transform Spectrometer. The new Oblique ECE diagnostic has entered operations during the 2006 experimental campaign at JET. The system provides lines of sight at 0, 10 and 22 with respect to the perpendicular to the toroidal field and two linear polarizations, one of which mostly ordinary and the other mostly extraordinary. Spectral analysis is performed in the bandwidth GHz using a multichannel Martin-Puplett interferometer. The time resolution was usually set at 10 ms/profile, with single-line equivalent spectral resolution of GHz. Antenna design The angles of sight for the diagnostic were chosen by trade-off between the opposite needs of having good spatial resolution, which becomes worse and worse as the angle increases, and of collecting the EC emission also from the bulk of the distribution, i.e., in the 18 IFP Activity Report

19 low energy range. Severe geometrical constraints are imposed by the location of the antenna, this being inserted in the vacuum vessel together with six oversized waveguides devoted to Reflectometry and Oblique ECE itself and their surrounding structure. As seen in Fig.1.6.1, the six waveguides are grouped in two horizontal rows with three waveguides in each of them. Fig Microwave access waveguides in octant 8 at JET. The two smooth-wall oblique ECE waveguides (inner diameter 32 mm), shown in a top view in Fig.1.6.1, share the same horizontal row with one of the reflectometer waveguides. The antenna has been designed with three flat mirrors and an ellipsoidal mirror, which is shared by the two lines of sight. The mirror arrangement was optimized using electromagnetic calculations at several frequencies in the band from 100 to 400 GHz. This solution is compact in length and leaves room for the external supports. Design of the Multichannel Fourier Transform Spectrometer Considering that the oblique ECE radiation is elliptically polarized, with significant variation of (X) and (O) fractions depending on the collection angle and the frequency, at least two linearly polarized orthogonal components (mostly O-mode and mostly X-mode at the lower frequencies) of the collected radiation must be made available for proper signal analysis. Besides this, 2nd harmonic, X-mode emission along the standard radial line of sight had to be available both for comparison with the oblique ECE and for backup (and, may-be, future substitution) of the Michelson interferometer presently used at JET. To allow detect all the (4+1) ECE signals, a previously installed single-channel Martin-Puplett interferometer was extended to accommodate up to 6 channels. In accordance with the new conceptual design the interferometer layout is split into two sets of components (see Fig.1.6.2). The first of these includes the group of moving arms, based on four helicoidally shaped roof top mirrors arranged on a wheel. The path-difference scan is provided by rotation of the wheel around its own axis. Worth being stressed is that in the case of the oblique ECE channels the reference arms are not truly independent because coupled channels (the pair from each antenna) bring perpendicular polarizations, and this spatial relationship has to be taken into account choosing 90 between the respective reflection points on the helicoidal mirror. The second group of components includes the fixed optical elements (mirrors and polarizing grids) of the reference arms, their supports and positioners, and the optics for signal input and output. The optical elements are mounted on a couple of optical boards in a T-shaped arrangement facing the array of rotating mirrors. The correct positioning of these boards in front of the moving array is assured trough an Ushaped spacer fastened around the wheel bearing, which also guarantees that the fixed optics can be removed and repositioned without loss of alignment. IFP Activity Report

20 1 Motor and reduction gear 2 Bearing 3 Spacer (mounting reference) 4 5 Back -plate (position reference) Wheel Optical encoder mounting Wheel cover z Motor support Input rectangular waveguides (perpendicular ECE) and tapers Input circular waveguides (oblique ECE) x y 11 Adjustable x-y positioners 12 Stiffening bars Fig Ensemble view of the interferometer. The optical components of the reference arms are mounted in the rear face of the vertical plane on the left side. The whole of the system described above has been modeled using the commercial GRASP (TICRA) software. Both offset and angular misalignments have been simulated. The loss of performance has been evaluated by computation of the coupling between the beam of the chosen channel and the waveguide mode both in forward (output waveguide) and backward (input waveguide) directions. The simulation also provides the electromagnetic field at the entrance of the output waveguide that brings the signal toward the detector. The detection chain includes a liquid-helium cooled InSb detector (hot electron bolometer), with 1 MHz bandwidth, optical NEP of 1 pw Hz -1/2, a low-noise differential preamplifier (40-80 db gain), and a remotely controlled amplifier for each channel. The acquisition of the data points, based on two fast digitizers boards (INCAA, 2MS/s per channel, 14 bit resolution) with 4 channels each and triggered by an optical encoder which provides the exact angular position of the roof-top mirror array. Performing the acquisition at equally spaced angular steps reduces the requirements on the uniformity of the rotation speed, which is limited by the vibrations. Calibration and first measurements A preliminary calibration of the 0 channel has been performed by comparison with other calibrated ECE diagnostics. At present, the calibration of the oblique channels relies on the computed level of EC emission corroborated with the emission measured at 0 degrees. This procedure has proved capable of data validation accurate enough to allow starting the physics analysis of the ECE spectra IFP Activity Report

21 1.7 Neutron spectrometry instruments and measurements on JET In collaboration with VR (Sweden) and IST (Portugal) two neutron spectrometry systems were installed and commissioned on JET in time for the start of the experimental campaign in The two spectrometers are now in regular use and provide diagnostic information on fast ion (mainly deuterium) dynamics. For the analysis the output of standard plasma interpretation codes is now coupled to a Monte Carlo code providing detailed simulations of neutron spectra under conditions of NBI and RF resonance heating. IFP has contributed specifically to the neutron spectrometry activities at JET with the construction of the Control & Monitoring system based on pulsed light sources (LED and LASER), and with the development of the Monte Carlo code. More generally, we contributed to the experimental programme at JET by leading some experiments and providing key diagnostic information in others. Of the two neutron spectrometers, TOFOR (Time of flight Optimized Rate) provides the best results for dd neutrons whereas MPRu (Magnetic proton recoil upgrade) is the only one that can measure both dd and dt neutrons. A photograph of TOFOR is shown in Fig The neutron time of flight is measured by detecting coincidence events in two sets of scintillation detectors. Each detector is equipped with a light fibre delivering light pulses from a LASER source and a less powerful LED source. The light pulses are used to simulate the scintillation light and provide a calibration reference. Fig The TOFOR spectrometer at JET The example of dd neutron spectrum shown in Fig was measured by TOFOR in a recent JET discharge with deuterium NBI. The data are shown as a time of flight spectrum where the average time of flight corresponds to a neutron energy of about 2.45 MeV. According to the TRANSP simulation the neutron emission consisted of beam-plasma neutrons with a small component due to beam-beam neutrons and negligible thermal neutron emission. The simulated neutron spectrum of Fig is based on a TRANSP simulation with no adjustable parameter except for the overall intensity. The newly developed Monte Carlo code produced the neutron spectrum using the TRANSP simulated fast ion distribution in phase space as input. The spectral shape is matched very accurately showing that the TRANSP analysis of the NBI fast ion motion including slowing down, diffusion and orbit effects was accurate in this case. Detailed comparison with simulations from RF codes PION and SELFO is in progress. IFP Activity Report

22 Fig Neutron time of flight spectrum from a JET discharge with on axis NBI heating. The fitted curve is the simulated spectrum based on TRANSP analysis of the fast deuteron population. 1.8 Gamma spectroscopy diagnostics for JET As part of the JET-EP2 programme IFP is leading the upgrade of the gamma spectrometers in use at JET (GRS project). Partners in the GRS project are IST (Lisboa), MEdC (Bucarest), Università di Milano Bicocca and Ioffe Institute (St Petersburg). In the last years gamma ray spectrometry has provided new insight into the physics of fast ions in JET, especially during the TTE campaign. Nuclear reaction gamma rays are produced by interaction between fast light nuclei, which can be fusion products, or ioncyclotron resonance frequency-driven ions, or NBI injected ions or plasma impurities. An example is given by alpha particles which, born by D-T reactions, during the slowing-down process in the plasma can react with impurities, in particular with beryllium. The reaction produces gamma rays of 4.44 MeV energy. The gamma ray intensity can be related to the alpha particle density and energy distribution. At present there are three gamma spectrometers in use at JET based on sodium iodide, NaI, and bismuth germanate, BGO scintillator detectors. Two of them are in use in the Roof Laboratory, one in a tangential view. They are all functional but with limitations in count rate (<50 khz total rate including a large background component due to neutrons), energy resolution (> 7% for the 662 kev gamma-rays from 137Cs) and large neutron-induced background. The project aim is to improve the performance of gamma spectrometry measurements at JET by designing and procuring new detectors and associated data acquisition and analysis tools. Three new detectors are being procured that will improve the gamma measurements in a number of ways. Energy resolution will be better that 0.2% in the case of the high purity germanium detector. The dynamic range will be improved by the use of fast scintillators and matching electronics (analogue and digital). Related to improved dynamic range is the improved time resolution. This will be limited by the available signal intensity from the plasma whereas it is now limited by the high neutron/gamma background combined with slow detector response. The key figure of merit is the count rate capability which shall exceed 0.5 MHz before pile-up and gain drifts begin to affect the detector response. These effects are unavoidable but can be quantitatively controlled through the combined use of a Control and Monitoring system and of digital data acquisition. It is expected that total throughput will exceed 2 MHz of total count rate of which a variable fraction will be from useful gamma events. Finally substantial neutron background reduction (factor >100) will be achieved for one of the detectors with the use of a LiH neutron attenuator. The choice of scintillation materials and other hardware for the gamma spectrometers at JET takes into account the latest developments in the field and the requirements for gamma spectrometry on ITER. Gamma spectrometry in ITER is a real challenge due to the large flux 22 IFP Activity Report

23 of 14 MeV neutrons; suitable neutron attenuators must be developed and the LiH attenuator designed for JET is a first step in that direction. ITER-related developments should include the testing of new detector materials based on high-z, heavy scintillators recently developed; these materials are fast and efficient which is promising for the development of high rate measurements with reduced neutron sensitivity. Where possible scintillators with low oxygen content should be used due to the unfavourable interaction of fast neutrons with oxygen leading to high background. On JET the choice will be to use lanthanum bromide (LaBr 3 ) and lutetium yttrium orthosilicate (LYSO) scintillators. LaBr 3 is available since early 2006 in the required dimensions (3 x3 ). It has excellent timing and light yield properties and is free from oxygen. Neutron sensitivity will be the object of laboratory tests at accelerator sources before installation on JET. LYSO is not as performing as LaBr 3 but has a higher efficiency. It is not a candidate for use on ITER but should provide high performance at JET under normal operating conditions. A comparative analysis of different scintillator crystals and of their performances was made using the code GEANT4, which simulates particle interactions with matter. The simulations have provided detector response functions with detailed information on the detector efficiency and the dependence on the environmental conditions. Besides the scintillators detectors used at present at JET (NaI and BGO) the two new crystals LaBr 3 and LYSO were simulated. The GEANT4 simulations have confirmed that a 3"x3" LaBr 3 crystal will have an efficiency greater than the present NaI, while a 3"x4" LYSO crystal will perform better than BGO in all respects. The simulations also showed a good spectral shape for both crystals, with good full-energy peak to Compton ratio and well-defined Compton edges; this is particularly true for the LaBr 3 crystal. To verify the validity of the GEANT4 simulations the response to gamma rays from a 60 Co source of an 1"x1" LaBr 3 has been simulated. A comparison between the measured data and simulations, shown in Fig.1.8.1, confirmed the validity of the simulation method. In particular, the spectral shape of the 60 Co source is in good agreement with the simulation in the energy range including the Compton edges. Fig Energy spectrum recorded in a 1 x1 LaBr 3 scintillator. The gamma source is 60 Co. The simulations were made with the GEANT code assuming an effective crystal size of 1 x1 (blue) and 0.9 x0.9 (red). A new possible application of lanthanum bromide crystal could be to measure the broadening of the gamma ray peaks. The broadening of the 4.44 MeV gamma ray peak is comparable to the expected LaBr 3 resolution. This is not ideal but can be tested at JET by simultaneous measurements with LaBr 3 and with a germanium detector. This has a much better energy resolution but is sensitive to damage by neutrons, and not suitable for routine fusion diagnostic applications. The hope is to demonstrate that LaBr 3 can replace germanium for this application, which would have an impact on alpha particle diagnostics on ITER. IFP Activity Report

24 24 IFP Activity Report

25 2. Theoretical research in plasma physics 2.1 Gaussian beam propagation, absorption and current drive generation Propagation of EC waves in tokamaks and the relevant power absorption (ECRH) and current drive (ECCD) have been widely investigated since long both theoretically and experimentally. Recently the interest in the investigation of these topics has been renewed by the planning of ECRH and ECCD systems for ITER. The main goals are bulk heating and current drive both to increase the plasma pulse length and to control neoclassical tearing modes (and possibly sawteeth) by means of localized current drive. In order to estimate the power needed, accurate predictions of ECRH and ECCD (in particular of the EC current density profile) are required. The predictive linear codes developed in the past may not be suitable to this goal, although the EC physics in ITER is linear due to the relatively low amount of power involved. ITER being a large device that will operate at high temperature, the approximations related to the different scale lengths and to the temperature need to be accurately revised in order to apply in it. Moreover, in the present design of the launching structure, astigmatic focused beams will be injected into the ITER plasma. Since the ECCD profile plays a key role in the MHD stabilization process, an extended capability of describing the propagation of general Gaussian beams in plasmas is required. A new code GRAY [D. Farina, AIP Conference Proc. 871, 77 (2006)] has been developed for the computation of the quasi-optical propagation, the power absorption and the current driven of a Gaussian beam of EC waves in a general tokamak equilibrium. Wave propagation is addressed in the framework of the complex eikonal approach, in which the Gaussian beam is modeled by a set of mutually interacting rays to allow including diffraction effects. These rays obey to the quasi-optical ray-tracing equations, coupled together through an additional constraint in the form of a partial differential equation. EC absorption and the driven current are computed on each ray of the beam solving a relativistic dispersion relation with the dielectric tensor expanded up to a given order in Larmor radius, and by means of an adjoint linear model for the current, which takes into account both trapped particle effects and wave polarization. The code GRAY has been successfully benchmarked against other EC codes. Extensive use of GRAY has been made to compute the EC current drive in different ITER scenarios for NTMs stabilization. 2.2 Interpretative ECE emission code A new interpretative code SPECE has been developed for the analysis of the electron cyclotron emission (ECE) in a tokamak plasma with the main goal of interpreting the Oblique ECE diagnostic recently implemented at JET. In addition, the code can be conveniently used to perform simulations relevant to ITER scenarios. The code solves the radiation transport equation along the ray trajectories for both a Maxwellian plasma and a non thermal plasma characterized by a distribution function that is the sum of drifting Maxwellian distributions. The ray trajectories are computed using the cold dispersion relation, while the absorption and emission coefficients are computed solving the fully relativistic dispersion relation. The effects due to the antenna pattern are also taken into account by means of a multi-rays calculation. The code has been specialized to compute the emitted intensity measured by the ECE diagnostics available at JET, and in particular by the new oblique system with three lines of sight at different toroidal angles (0, 10 and 22 with respect to the perpendicular to the toroidal magnetic field) and two linear polarizations. The magnetic equilibrium of a JET shot is obtained from the EFIT code and the density and temperature profiles from the LIDAR and the Michelson interferometer, respectively. The IFP Activity Report

26 possible non-maxwellian character of the emission can be investigated by a parametric analysis #[email protected] T A [kev] o XM 10 o XM 22 o XM z [cm] o,22 o 0 o f [GHz] R [cm] Fig Magnetic equilibrium for a typical JET shot and lines of sight of the ECE antennas at 0, 10 and 22. Radiative temperature as a function of frequency for the three line of sights and quasi-vertical linear polarization (almost extraordinary mode), as simulated by the SPECE code for a Maxwellian plasma 2.3 Magnetohydrodynamic equations for multicomponent plasmas The physics of plasmas of mixed composition is of increasing importance both in laboratory experiments and in space plasmas. In the physics of magnetically confined plasmas of interest for thermonuclear fusion, the problem of controlling the impurity concentration has become of outstanding importance as it sets severe limits on the energy confinement time, the net-power yield and the tolerable wall-load of a reactor. The role of impurities is fundamental (even if not fully understood) also as regards the mechanisms leading to edge localized modes (ELMs) and edge thermal instabilities in tokamaks. In order to provide heat and particle exhaust while allowing impurity entrainment, existing and planned tokamaks are generally designed with a magnetic-separatrix boundary separating the bulk plasma from a divertor region. There are indications that plasma flow in the divertor region can exhibit complex behavior including flow reversal of the main plasma components and impurities. Owing to the increased awareness of the important role of the flows in the divertor, efforts are being devoted to characterize the plasma and impurity flows in the divertor channel. Numerical calculations based on the traditional fluid equations are generally used to this purpose. The classical system of equations by Braginskii have provided the basis to most problems of plasma dynamics in which the particles mean free path λ m.f.p. <<L, the typical scale length. However the applicability of this system is strictly limited to a plasma of electrons, a single species of ions and, at most, only trace impurities. In collaboration with Dr. N. Bobrova and S.A,. Sasorov we have addressed the task of reformulating from first principles a set of MHD equations for a multispecies magnetized plasma with arbitrary concentrations, overcoming some limitations of the Braginskii system. From kinetic theory we have derived a full set of transport coefficients applicable when the ion species have arbitrary 26 IFP Activity Report

27 concentrations, space and time dependent, but very different atomic masses. The method we adopted to obtain a hydrodynamic description of the problem from moments of the kinetic distribution functions for the electrons and two species of ions is quite different from the traditional Chapman-Enskog method. The background distributions are assumed to be Maxwellians with slowly varying parameters appropriate for a Local Thermodynamic Equilibrium (LTE) description. The first-order perturbations in the parameter λ m.f.p. /L are obtained through a representation in spherical harmonics respectively of scalar, vector and tensor components. The solution of the scalar, vector and tensor parts of the linearized kinetic equation for the electrons is expressed through the matrix elements of the inverted collision operator. The first order distribution function for the lighter ion species is obtained from appropriate substitutions in the corresponding expressions for the electrons. This is possible due to a similarity between the equations for the electrons and the ions that becomes apparent only in the vector and tensor parts of the representation in spherical harmonic, and is a specific merit of using this type of expansion. For the heavier ion species, when the relative role of the collisions between ions becomes arbitrary, the vector and tensor parts of the equations have to be solved through the matrix of the inverted collision operator. The vector components of the kinetic equations for the electrons and the two species of ions are related to each other. The method adopted allows to solve them successively as if they were independent. Then the constraint imposed by the solubility conditions determines the impurity flux through the gradient of macroscopic parameters (thermodynamic forces). This major result greatly contributes to an improved understanding of the divertor flow problems mentioned above. 2.4 Critical island width for NTM modes High temperature tokamaks are susceptible to NTMs that feed on the free energy provided by a helical perturbation (flattening) of the bootstrap current on q rational surfaces. The NTMs grow as magnetic islands that saturate at widths that are detrimental for the tokamak equilibrium and performance. NTMs are known to be metastable, featuring a threshold island size and a critical beta, above which they are unstable. The physics determining the threshold is not yet completely understood, and depends on a variety of elements, including the ion polarization current that represents a ion finite inertia effect. This term is in turn related to the island rotation frequency that depends on several dissipative processes: classical resistivity and heat conductivity, collisionless Landau damping, perpendicular density/energy diffusion (anomalous), perpendicular anomalous viscosity and neoclassical flow damping and symmetry breaking. The complete physical picture of these effects is still an open issue. In collaboration with the University of Saskatchewan (Canada) a stabilising role has been found of the neoclassical enhancement of the polarisation current, associated with a coupling of the transverse and longitudinal flows in a torus. Furthermore it has been found that finite parallel heat conductivity along the magnetic field in an island drives a variation of the plasma temperature (and pressure) along the field lines that partially restores the pressure gradient across the magnetic island reducing the destabilising bootstrap current effect, thereby modifying the shape and extent of the NTM metastable region. This affects significantly both the critical island width and beta for mode onset and is currently under development the theoretical model to estimate more realistically the ECCD required for mode control and suppression. Several papers have been published on this subject that represents still a lively and important research. IFP Activity Report

28 2.5 Effects of sheared rotation on ITG modes stability There is wide experimental evidence that tokamak plasmas, either in Ohmic regimes or during RF injection with no net input of angular momentum, develop a toroidal rotation as if the source of angular momentum were localized at the plasma perifery. As an example, in Alcator C-Mod, without an external momentum source, at the L-H transition a co-current toroidal rotation of the plasma appears at the edge, which then propagates towards the core and eventually peaks on-axis. The physical mechanism generating the so-called spontaneous plasma rotation is not yet clear and several hypotheses have been advanced. The search of the origin of such rotation is stimulated because as J.E. Rice said at 21 st IAEA Fusion Energy Conference The spontaneous rotation observed in many tokamaks may provide the necessary velocity for RWN stabilization in certain ITER operational scenarii,. A theory of spontaneous momentum generation due to the toroidally asymmetric excitation of radially localized ITG modes in the presence of a radial profile of the toroidal ion velocity, has been formulated first by B. Coppi. According to this theory, the toroidal rotation of the plasma column when no net momentum is injected from the outside (neither by RF, nor by NBI) is determined by the transport properties of the plasma, which in turn are governed by modes that are made unstable by the plasma configuration (typically, electrostatic drift modes excited by pressure gradients). The source of momentum can be sought for at the plasma edge, where a steep density profile can excite modes with the toroidal component of the phase velocity lying in the direction of the electron diamagnetic velocity, v *ne =-D B dn e /dx (counter-current direction), where D B =ct e /eb 0, and x is the slab coordinate corresponding to the minor radius in toroidal geometry. The particles with the parallel component of the velocity, v, in the direction of v *ne diffuse away and hit the material wall, where their momentum is dissipated. As a consequence, the plasma column acquires an opposite angular momentum is in the ion diamagnetic direction v *i (co-current direction) in its peripheral zone. With the aim of investigating the characteristics of the electrostatic modes that are supposed to transport the toroidal momentum from the plasma periphery inwards, a systematic analytical study of the stability properties of ITG modes in the presence of a parallel (to the external magnetic field) ion velocity, in a 1-dim slab geometry, has been started. The linear dispersion of the ITG modes in the presence of a non uniform ion velocity in the direction of the sheared equilibrium magnetic field, has been investigated in the frame of the two-fluid guiding-center approximation. The effects on the dispersion of the magnetic field inhomogeneity and curvature have been taken into account by means of an effective gravitational-like drift velocity and of the contribution of the diamagnetic velocity due to the magnetic-field inhomogeneity. The dependence of the stability of the ITG modes on key plasma parameters, as for example the ion temperature scale length, L T =-T i /(dt i /dx), the velocity scale length, L U =-C s /(du /dx), the ion to electron temperature ratio, τ, the ion effective charge, Z eff, the parameter η i = dlnt i /dlnn i, has been also investigated in detail. Moreover, for given spatial profiles of the physical parameters and the fluctuation energy spectra in the k -k plane, with the restriction k / k <<1, the transverse (to the magnetic field) quasilinear fluxes of the ion thermal energy and the longitudinal momentum have been calculated, together with the corresponding diffusion coefficients. Several spatial profiles of the density, the temperature, the magnetic shear and the velocity shear have been analyzed. A non-zero du /dx has turned out to be mainly destabilizing at a linear level. An interesting result is that a Kelvin-Helmoltz-like instability can be excited for flat T i profiles and become dominant at low η i values, which effect is particularly important at the high field side of the plasma slab. The quasilinear fluxes of the ion pressure and of the parallel momentum have been calculated using the mixing length rule for the turbulence saturation. It has been observed that hollow momentum radial profiles (occurring when a momentum source appears at the plasma boundary) can give rise to an anomalous inward momentum diffusion. The anomalous diffusion coefficient of the longitudinal momentum has been also calculated 28 IFP Activity Report

29 and its scalings worked out. Recently, dissipative effects have been introduced in a simple, constant-b field model, in order to investigate the effects of a velocity shear in the presence of both viscosity and energy dissipation. 2.6 Microislands and transport in tokamaks The interaction between ions and the ensemble of microislands (whose half-width is smaller than the Larmor radius of the ions), localized on rational surfaces, has been studied in tokamak geometry. It has been shown that energy is pumped from the ions to the islands, as a consequence of the combined effects of nonlinearity and toroidicity in the equation of motion of the ions. The conditions for the formation of a stationary system of microislands are given. The presence of microislands determines an electron heat conductivity, which depends on their density and on the macroscopic equilibrium. Examples of scalings of the electron confinement time, predicted in zero-dimensional approximation, are given for typical tokamak conditions. 2.7 Electron holes in a non-uniform collisionless plasma Among the several physical processes accompanying wave-plasma interactions, particular interest deserve electron and ion holes (EHs and IHs) in phase space, which are typical nonlinear kinetic structures capable of producing macroscopic measurable effects in space plasmas. Generally speaking, EHs and IHs are non-equilibrium (i.e., non-maxwellian) quasi-stationary non-linear solutions of the Vlasov-Maxwell equations characterized by a localized (both in velocity and in physical space) depletion of the distribution function and a corresponding spatially localized electromagnetic field pattern. E δn e Fig Normalized electric field E (upper frame) and electron density δn e (lower frame) fluctuations versus the spatial coordinate x/λ De, at t = 720/ω pe. Around x = 500λ De, the background plasma density decreases by 40 % over a spatial interval of L n = 10λ De. The dipolar structures in the E-field, corresponding to density holes in the lower frame, represent the signature of propagating electron holes. In order to investigate the possibility of generating EHs by means of externally driven electrostatic (ES) waves, a Vlasov-Maxwell numerical code with open boundary conditions has been implemented and the propagation of a finite amplitude ES wave-packet in a nonuniform plasma has been studied. The wave-packet is excited in the spatial interval 0<x<100 (in units of λ De ) at a given frequency ω (in units of ω pe ), then it propagates towards increasing x-values seeing different background density profiles. In the excitation region ω>ω pe and k<1, and therefore the wave-packet propagates almost undamped. Around x 500, the density is alternatively made to increase (up to ω<ω pe ) or decrease (down to k 1). Correspondingly, the wave-packet is reflected back or is strongly Landau-damped, therefore it cannot propagate further on. Numerical simulations show that in the spatial region not allowed by the linear theory, namely x>500, several density holes are produced continuously, which propagates IFP Activity Report

30 forward at a constant velocity v EH, containing a dipole ES field and suffering no damping at all (see Fig.2.7.1). In Fig the hole in the electron distribution function, corresponding to the density dip at x=800, is shown. As seen, the hole is localized at v x 0.28v the, which represents the constant velocity of its motion through the plasma. Generally speaking, EHs have been observed with v EH ranging from a fraction of v the to 2v the. In any case v EH is much less than the phase velocity of the parent wave-packet. If v EH <<v the then a bump in the ion density accompanies the formation of the EH. These ES solitary waves have an intrinsically kinetic nature, although they manifest macroscopic features like a single-cycle ES field and a depleted electron density. Fig The electron distribution function in the phase space (x/λ De,v x /v the ), at t = 720/ω pe. The hole corresponds to the feature at x 800λ De, in Fig v x The rapid technological progress in high-peak-power, ultra-short-pulse lasers makes available hundred-terawatt and even petawatt sources, that allow one to investigate experimentally extreme states of matter, where electrons are accelerated to p osc >>m e c 2 by the laser field (in the order of V/cm), and ions are driven up to several hundreds MeV by the induced charge separation. When an ultra-intense electromagnetic (EM) pulse propagates in a plasma, several non-linear phenomena are excited, as, for example, laser frequency variation, high-order harmonic generation, non-linear spatial structures (plasma channels, relativistic solitons, vortices), ultra-intense electrostatic (ES) and magnetic fields, and electron and ion acceleration. Several theoretical models, fluid and kinetic, aimed at describing the plasma response to a relativistically-intense EM field, depending on the interaction regime, have been investigated and developed at IFP. In particular, two aspects of the interaction of ultraintense EM radiation with a pre-existing plasma, of special interest both from the fundamental and the applicative points of view, have been considered: (a) EM equilibria corresponding to so called relativistic EM solitons (RES) in a warm plasma, and (b) proton acceleration driven by the interaction of an ultraintense and ultrashort laser pulse with a thin solid target. (a) Theoretical modelling of circularly polarized RES in collisionless warm plasmas was previously carried out, with the aim of characterizing the quasi-stationary spatial structures observed in multi-dimensional particle-in-cell (PIC) simulations. In , in the frame of the CNRS-CNR France-Italy Agreement on Joint Project of Research Interaction of ultraintense lasers with matter: properties of the transport of relativistic electrons in the target and ion acceleration, a comparative study of the ES solitons observed during 1D particle-in-cell simulations of the interaction of an intense EM radiation with a under-dense plasma slab, with those predicted by theory, has been carried out successfully. Simulations made using the 1D2V relativistic PIC code EUTERPE have shown that, for high enough laser intensities, (I> W/cm 2 ), propagating in an under-dense plasma (initially, n e0 =0.3n cr, where n cr =m e ω 2 0 /4πe 2, ω 0 being the laser frequency), a pulsating regime of stimulated Brillouin backx 2.8 Ultraintense electromagnetic radiation in plasmas 30 IFP Activity Report

31 scattering (SBBS) sets in, followed after 10 3 ω 0-1 by a quiescent phase with a reflectivity as low as 5%. This latter state is characterized by the presence of several density cavities, where almost all plasma density has been evacuated (see blue line in Fig.2.8.1a), which prevents the resonant SBBS amplification and enables strong electron and ion heating. Part of the incident EM energy is trapped inside the density holes, where it is amplified. Moreover, the frequency of the trapped radiation is down-shifted to ω 0.25ω 0, and electrons are strongly heated, from the initial temperature of 500eV to the final temperature T e 50keV. An analytical model has been developed to describe the structure of the first plasma cavity, which appears during the laser-plasma interaction. As seen by comparing the same color lines in Fig.2.8.1a and 1b, the quasi-stationary spatial distributions of the transverse electric field (red lines), of the magnetic field (green lines), and of the ion density (blue lines), resulting from the numerical simulations are well reproduced by the analytical model. When full density depletion takes place, the vacuum solution of the 1D Maxwell equations is a(x)=a pk cos (ωx/c), with the peak amplitude a pk proportional to T e 1/2. This shows that the finite plasma temperature must be necessarily taken into account for a correct modeling of the plasma soliton. Fig The one-dimensional soliton structure from the kinetic numerical simulation (upper frame, a), at t = /ω 0, and from the analytical quasi-stationary model (lower frame, b), where ω 0 is the laser angular frequency. Red lines correspond to the transverse electric field, green lines to the transverse magnetic field, and blue lines to the ion density. Presently, the analysis of linearly polarized 2-dim RES is being carried out, in order to compare analytical results with new numerical ones. Suitable time averaging procedures have been introduced in order to manage the presence of harmonics related to the linear polarization of the EM field. Both s-polarized and p-polarized trapped EM fields are being considered. (b) Ultra-high intensity lasers are proven to be particularly suitable for ion acceleration to energies above hundreds kev, and even in the multi MeV range, due to their interaction with high-density targets. The acceleration process is a consequence of the huge charge separation that is induced in the matter under the action of the laser field. When the ultra intense laser pulse (with intensity I L >10 19 W/cm 2, wavelength λ 1 µm and duration τ<1 ps) irradiates the front side of a thin (few tens of µm) high density target, EM radiation is converted into kinetic energy of a hot (T few MeV for multi-tw or PW class lasers) collisionless electron population with high efficiency (around 20 or 30 %). These electrons move through the solid target and appear on its rear side, where a cloud of relativistic electrons is formed, that extends out of the target for several Debye lengths, giving rise to an extremely intense longitudinal ES field, which is responsible for the ion acceleration. In the early stage of the interaction, after the onset of the negatively charged hot electron cloud at the rear side of the target, the ions lying in the first atomic layers feel the associated ultraintense ES field and start to be strongly accelerated without appreciably perturbing the quasi- IFP Activity Report

32 static hot electron spatial distribution. Later on, after the density of the accelerated ions has become a non-negligible fraction of the hot electron density, the plasma expands as a whole and cools down adiabatically and due to the energy transfer to the accelerated ions. The most energetic part of the ion energy spectrum is produced during the early acceleration phase, when the highest values of electric field are achieved. Then it is meaningful to look for a quasi-stationary distribution of hot electrons with constant temperature, and to calculate the test-ion acceleration in the corresponding field. In order to model the spatial distribution of the accelerating ES potential, the 1D Poisson equation has been analytically solved, assuming a Maxwell-Boltzmann distribution for the bound electrons, while unbound electrons are considered lost from the system. It turns out that the potential becomes zero, together with the corresponding electric field and electron density, at a finite distance from the rear face of the solid target. A full solution of the problem requires the specification of the maximum energy of the electrons in the laser field, ε max. This quantity can be related directly to the experimental parameters, or determined either on physical basis, for example as the maximum kinetic energy acquired by an electron in the field of a given EM wave, or by a more accurate treatment of the laser energy coupling with electrons. The maximum energy, ε i, an ion can acquire in the consistent ES field can then be obtained once T and ε max are known. The model has been worked out in order to make it applicable to ultra-relativistic electron temperatures, as it is generally the case in experiments with multi-tw lasers. An empirical scaling law, ε max /T e =A+B*log(E L ), with E L the laser energy, has been determined by inspecting the experimental data available in the literature and used to predict the maximum ion energy achievable for given I L, E L, and d values. The ion energy spectrum has been also calculated, and satisfactorily compared with experimental results. Worth being noticed is that the interpretation by means of PIC codes of recent experimental measurements of the accelerating electric field shows that, in the early stage of the interaction when most of the ion acceleration takes place, the electric field becomes negligible, or even zero, at a finite distance from the target, which is consistent with our model. (c) The original quasineutrality of a plasma at rest is heavily perturbed when the electrons are induced to oscillate relativistically by a superintense electromagnetic radiation beam. This represents one of the major difficulties when studying the propagation of intense linearly polarized electromagnetic waves in plasmas. Thereby particular attention has to be dedicated to the effective relativistic increase of the critical density and the density of maximum electromagnetic energy deposition for applications. The fundamental relativistic equations of electrodynamics have been reconsidered in the case of relativistically intense linearly- and circularly-polarized electromagnetic waves acting on an electron fluid element, paying particular attention to the competing effects of the Lorentz transformation to the reference system moving with the oscillating electrons (that is, of the increase of the density due to the space contraction in the direction of motion), and of the relativistic increase of the electron mass. Physical models have been separately developed for linear and circular wave polarization to solve the apparent paradox. 32 IFP Activity Report

33 3. ITER relevant studies 3.1 Capabilities of ECRH/ECCD system in ITER The main goal of the physics analysis of the ITER ECRH/ECCD system during 2005 has been to evaluate the performance of the Upper Launcher both in terms of the required steering range and of the figure of merit for NTMs stabilization (η NTM =J ECCD /J bs ), for the (2,1) and (3,2) modes and three reference ITER scenarios, namely the inductive scenario 2, the hybrid scenario 3a and the low q scenario 5. The two launcher designs, the Remote Steering (RS) and the Front Steering (FS) scheme, have been considered in this study. Low values of η NTM have been found in case of the RS design for all the reference cases, except for q=2 in the reference Scenario 2, the only case where the physics goal η NTM 1.2 has been met, thanks to the large size of the astigmatic beams leading to quite broad driven current profiles. For the FS launcher, using a front-steering mirror that provides optimum focusing and the possibility of a wide steering range, quite good figures of merit have been obtained for all reference Scenarios: η NTM 2 for all (2,1) modes and η NTM 1.8 for all (3,2) modes. Besides the analysis in ITER plasmas at the nominal magnetic field B=5.3 T, the capability to drive efficient and well localized co-current in a range of relevant surfaces in ELMy-H mode ITER plasmas at low magnetic fields have been explored up to half field with respect to the reference magnetic field. The analysis showed that ECCD using the upper launcher in plasmas with reduced field is possible using the O1-mode down to B T /B T0 around 0.85 and in a similar window at half field using the X2 mode. NTM stabilization efficiency is found to be sufficient in all these cases, exceeding η NTM = 1.2 by a margin comparable to that at full field in most cases. In 2006 an optimization study of the complete ECCD launcher (Equatorial Launcher (EL) and Upper Launcher (UL) has been carried out. Here, the emphasis has been on finding an optimized task sharing for the two systems.. Since the Front Steering (FS) offers appreciable reserve in η NTM, a new variant of the UL, called Extended Physics Launcher (EPL) has been designed (by CRPP), which can improve the capabilities of the system in terms of sawteeth stabilization by adopting different deposition ranges for the upper and the lower mirrors in the UL, still maintaining acceptable η NTM over the full range. Calculations done for the EL have pointed out that the present design should be modified in order to drive a counter-current in addition to the co-current considered so far. This will increase both the flexibility of the system and the possibility to decouple heating and current drive, which is beneficial for the control of the discharge and for enhancing the operational domain (scenario control). For instance, calculations done for the advanced Scenario 4 have shown that a large flexibility for control of central q would be obtained by IFP Activity Report

34 driving co- or counter-current close to the center. These views are now shared by the ITPA- SSO group, to which the results have been presented in November Studies for the ITER ECRH/ECCD system This section deals with activities performed in support to the European contribution to the ITER project in the field of ECRH&ECCD applications, in particular the Upper Launcher and the 170 GHz gyrotron a) ITER ECRH&ECCD launchers The physical requirements foreseen for an ECRH&ECCD application [see section 3.1] determine physical and technical constraints on the ECW launcher. The launcher optimization aims at the smallest possible beam size in absorption regions where ECCD current has to be driven and/or plasma ECH is localized, while preserving a suitable steering range of the beam across the plasma cross section. The main goal of the ITER EC H&CD Upper launcher is the stabilization of NTMs. The launcher consists of a corrugated waveguide, and of a set of mirrors, one movable for providing beam steering. Two arrangements are considered for the UL, one with the steering mirror in front to the output aperture of a circular corrugated waveguide close to the plasma. This Front Steering (FS) arrangement is most common in present experiments, and provides a beam with steering range and a radius at absorption adequate for achieving NTM stabilization in all ITER scenarios considered at 20 MW injected power. In the second arrangement the steering mirror is placed at the input of a square corrugated waveguide of length L = 4a 2 λ, which images the input beam and the injection angle at the waveguide output. In order to limit the length (L 4.4 m), the size of the square waveguide is a = 44mm. The imaging properties of the square waveguide are acceptable (transmitted power 95% only for a limited steering range ±12. A mirror is needed for focusing, which also restricts the useful steering range. The optimization of the mirror surface consists in looking for the better trade-off between beam focusing and steering range extension. The advantage of this Remote Steering (RS) arrangement is that the flexible pipes for mirror cooling are located far from the hot plasma, contrarily to the FS system. The activity on the ITER ECRH&ECCD Upper launcher consisted in the detailed analysis, from a mm-wave design point of view, of the two RS launchers. Beam optics calculations were performed using the latest design of the RS launcher. In the so called dogleg option for the RS ECRH launcher two double curvature mirrors are used to direct and focus the EC beams in ITER plasma with a sufficient steering capability. The complexity of this launcher led necessarily to a beam description that uses general astigmatism theory. The correct orientation for both spot ellipse and phase ellipse, whose orientation changes with propagation even in free space for generally astigmatic beams, is one of the input key parameters to perform realistic calculations with beam tracing codes. These calculations aim at the characterization of the launching system in terms of localized heating and current drive efficiency. With a major/minor axes ratio in relevant absorption regions ranging from 2.3 to 4.4 in the cases examined. Furthermore, the major axis of the resulting spot ellipses presents a final orientation is close to a vertical direction with respect to the equatorial plane of ITER. Some aberrations of the output beams are expected for larger scanning angles, which are not taken into account by Gaussian treatment of beam propagation. The physical optics code GRASP (TICRA) was used in order to evaluate the beam patterns at 0 and ±12 on a plane placed at around 2 m from the mirror, near the resonance in the plasma. Fig shows the effects of the mirror curvature (an increase of beam width of less than 5%). The effect of the mirror truncation, with the inclusion of real mirror shape and the possible presence of surrounding objects will be the object of future refinements. 34 IFP Activity Report

35 Fig Contour plots of beam patterns for the spherical (left) and hyperbolic (right) mirrors at 0 and ±12 of steering angles. Levels are shown by 5 db steps. b) Mirror reflectivity and surface erosion In most applications of microwaves the power reflected at the Snell s angle is lower than predicted, even for good quality mirrors, because of a non-smooth shape of the real surface. Scope of this work is twofold: first, to work out a model for loss enhancement based on the effective area increase in rough surfaces, applicable to the case in which the wavelength is much longer than roughness (both amplitude and scale length), and the skin depth is not necessarily much smaller than roughness. Second, to apply surface texturing for the evaluation of the likely effect of roughness on long-term mirror reflectivity. Measured extra-losses at reflection of millimeter wave beams from metallic surfaces are consistent with the assumption that they are due to the effective surface increase created by roughness. The agreement between prediction and measurement is achieved with different surface textures and PSD function. In order to validate the model a direct comparison between the losses enhancement factor γ and surface roughness is necessary, in particular at high roughness, since available data are consistent with different surface topologies (see Fig.3.2.2). loss enhancement measured; 35 GHz λ c =33 σ; 35 GHz λ c =33 σ; 170 GHz loss enhancement measured; 35 GHz λ g =2.1σ; 35 GHz λ g =2.1σ; 170 GHz σ(µm) σ(µm) Fig γ factor dependence with σ. Left: machined copper surface, stochastic on scale lengths shorter than 33s. Right: periodic surface having a wavelength peaked at 2.1s. The calculations are made for two frequencies, and compared with experimental data at 35 GHz [Tischer, IEEE Transactions MTT-24 (1976)]. Assuming that the area-model is correct, purely stochastic processes like erosion/redeposition should not cause a significant loss enhancement per se, at realistic erosion damage. Mirror surface can be machined to low losses (σ 0.2 µm for copper), and ageing do not necessarily cause severe long-term reflectivity degradation. Therefore erosion IFP Activity Report

36 should not be a major problem for plasma facing mirrors, while the main focus should be on surface contamination. c)high power calorimetric matched load The activity on the design and construction of a family of compact matched loads for high power millimeter wavelength beams absorption has been undertaken in IFP/CNR since some years ago. The designed loads can be used for atmospheric and vacuum operations. Suited for high power, millimeter wave ECRH applications in the field of plasma physics, they can be useful either for CW (up to 2MW) or short pulses (2MW, 0.1s) applications. They are useful not only for matched beam sinking but also to have a precise bolometric measurement of the mean absorbed power that is removed by the water flowing into the spiral cooling channels. Some prototypes can be matched to evacuated transmission lines. The different kind of load in the family differs mainly in the way in which heat is removed and calorimetry is performed. The activity carried out during the last two years consists mainly in the development of a new load capable of 2MW in CW, as required by the project of a 2MW CW and short pulse matched load. The load is built within the European 2MW coaxial cavity gyration development programme. (EFDA task TW5-THHE-CCGDS2 - TW6-THHE-CCGDS4). The design is based on the same concept of the loads designed and built in IFP/CNR during the previous years, that is an integrating copper sphere coated on the inside with a partially absorbing ceramic layer. A new model describing the power distribution has been developed, that takes into account a variable thickness of the absorbing coating along the meridian, the proper shape of the spreading mirror, the frequency of the incoming radiation and the shape of the input beam. A more uniform distribution of the absorbed power is obtained by a proper combination of those free parameters. An annular phase scrambling mirror has also been designed to prevent overheating of the load surface around the mirror, in case of beam with high side-lobe content. A prototype load to be used for CW application is presently under construction (see Fig.3.2.3). In this case, forced water-cooling of the entire surface is achieved in 16 spiral channels electroformed on the usual copper shell, machined to required precision by plate turning. Fig A half shell of the 2 MW, 170 GHz CW electroformed copper load with open channels (left). Calculated temperature distribution on the hot wall (centre) and on water side (right) is shown. High power tests on short-pulse loads have been done during winter 2005 using a double frequency gyrotron, 105GHz/600kW for 0.5 s and 140GHz/800kW for 1s. In addition, high power test have been performed at 140 GHz, 800 kw each half shell (equivalent to 1.6MW in total), 0.1s duration. A prototype of un-cooled dummy load has been used to make characterization tests on the beam produced by the prototype of 2MW coaxial cavity gyrotron. IR imaging of the outside surface allowed a good control on the real power distribution into the inner coating and also hot spots could be easily detected 36 IFP Activity Report

37 3.3 Development of innovative microwave Diplexer/Combiner A primary role of ECRH in ITER will be control and stabilization of the magnetic islands associated to the NTMs. In the phase in which the island width is less than the ECRH power deposition width, a modulated injection (in phase with the island O-point passage in the absorption location) is found more effective than continuous injection. Modulating the gyrotron pulses has the drawback of reducing the average power delivered to the task to around 50%. This reduction was overcome directing the power alternatively toward one of two launchers toroidally or poloidally displaced in a way to hit the island O-point at any time. This can be accomplished at the required speed (a few khz) only with a fast switching that relies on electronics, rather than on mechanical components. To this purpose, a whole family of new fast switching components (diplexers) has been developed in Europe, based either on resonant loops or on beam interference and realized with quasi-optical or waveguide components. Their output is controlled by means of small shifts of the source frequency, that can be varied electronically. In particular, an original diplexer has been developed in IFP that makes use of the beam splitting properties of a rectangular corrugated waveguide with aperture D much greater than the wavelength and cut at a proper length =2D 2 /λ. The diplexer is realized arranging the waveguides in a configuration with one or more resonating rings. A theoretical investigation of the performances showed that this configuration can have several advantages with respect to other waveguide and quasi-optical schemes, mainly in terms of compactness and ease of construction as a single piece. The exploitation of a second input port would allow the combination of beams from different gyrotrons (with nearly the same frequency) into the same transmission line. The device can then be used also as beam combiner. Such a device would allow more flexible arrangements for power beam routing. Putting diplexers and combiners in cascade, the power flow could be controlled with very fast switching between different launching locations. In the ITER case these could be represented by two toroidally displaced Upper ports and the Equatorial launcher. A fast controllable system could provide a most efficient use of the power when ECRH is used as a control tool for instabilities. The power needed could be switched only when strictly required, leaving the rest available for the normal operation. In1 M M In2 Out1 M M Out2 Fig Diplexer-combiner based on a rectangular-waveguide resonant configuration. Plans for further development and low-power measurements of a prototype diplexer, as well as for its application to the ECRH transmission line of FTU (for power testing) are under consideration. A demonstration of efficient power handling capability and reliable output control is required before proposals for integration of diplexers in present or future transmission lines can be concretely made. 3.4 Contribution to ITER reflectometry diagnostics EFDA started, within its 2005 Technology Workprogramme, a set of European Union/ Russian Federation Collaboration tasks. IFP is the European partner of Kurchatov Institute in task TW5-TPDS-DIARFB2, subtask 2.2, for developing a suitable solution for the vacuum IFP Activity Report

38 window for ITER reflectometry. The task started in January IFP's role is participating in the selection of the most promising conceptual designs and assist the RF partner in coping with ITER requirements. 3.5 Plasma microtorch for ITER wall diagnostic A preliminary investigation of the feasibility of a wall diagnostic using a plasma microjet has been carried out. The basic idea is to sputter the first layers of the surface with positive ions supplied by a plasma. Neutrals coming out from the surface are excited by the plasma itself and detected by Optical Emission Spectroscopy (OES). Positive primary ions are delivered by a DC discharge with a capillary used as anode. Efforts have been paid in the first part of the work to reproduce a microdischarge first in a cathodic way and then in an anodic way. The anodic microdischarge showed the same features as the current-voltage curve for the cathodic discharge. Its optical performances are superior to those of the cathodic one since more excited ions are produced for the same operating parameters. The plasma density is of the same order of magnitude as in the cathodic case. The production of both excited neutrals and ions strongly depends on the pressure, and the anode-cathode gap distance; much less on the gas flow rate. The intensity of the signal from the surface depends on the pressure, the discharge current and the gap distance. The intensity is not linearly related to the primary ion current, the signal depending on both local melting and sputtering taking place on the surface. Heat transfer to the surface is the driving factor since no signal at all was collected in samples melting at high temperature. Our tests finally demonstrated that the diagnostic cannot be realized at high pressure as envisaged. However, several issues evidenced in the experimentation are not yet clear and will require further studies. 38 IFP Activity Report

39 4. Microwave applications and instrumental facilities for wave plasma physics 4.1 Testing of the Flight Model-Flight Spares components for Planck-LFI instrument PLANCK is the ESA mission (to be launched in 2008) designed to measure the anisotropy spectrum of the Cosmic Micro-wave Background (CMB) to the full extent of cosmological relevance and make quantitative measurements of CMB polarization. Its optical system consists of a Gregorian telescope coupled with two instruments, High- and Low- Frequency Instrument (HFI and LFI), on the focal surface. The HFI includes an array of bolometers from 84GHz to 1THz. The LFI includes an array of pseudo-correlation radiometers spanning the range GHz in three 20% frequency bands, centered at 30, 44 and 70 GHz, with 2, 3, and 6 array elements. Each LFI radiometric chain consists of a front-end section, cooled at 20ºK, with a corrugated horn feeding an Orthomode Transducer (OMT) that splits radiation in two linear orthogonal polarizations and feeds the Front End Module, that compares the input power with the emission from a 4ºK reference load. Fig LFI on the support frame, ready for integration on the satellite payload (courtesy Alenia Spazio div. Laben). Fig Comparison of the measured and the simulated beam pattern at 70GHz The signal is delivered to the Back End Module for detection with two pairs of long rectangular waveguides, one pair for each polarization, grouped in a single module.the 11 antennas and the intricate pattern of waveguide modules are clearly visible in Fig IFP has been in charge of the tests on LFI passive components since the prototyping phase in During 2005 and 2006, the Flight Module and Flight Spare components were successfully tested. The measurement techniques were improved with respect to those used in previous years, allowing a precise assessment of performance before and after vibration, and a validation of the manufacturing process. The horns test matrix was expanded with respect to the original plan, allowing the detection of any problems in the integration with OMTs by inspection of the sidelobes in the co- and cross-polar pattern. Optical simulations of the LFI main beam have been carried out considering the measured feed as source and computing the pattern scattered by the two reflectors of the Planck telescope using the electromagnetic software GRASP (TICRA). The results reflect the high quality of feed manufacturing and the high level consistency between simulation and measurements at feed level (see Fig 4.1.2). IFP Activity Report

40 IFP also participates to the calibration campaign of the LFI until its delivery to ALCATEL ALENIA SPACE France for the next stage of integration before launch. 4.2 A cusp plasma device for plasma studies and technological applications A steady state plasma device has been built at IFP. The magnetic field confinement has a cusp configuration. A 3D view of the plasma device is shown in Fig Fig D layout of the cusp experimental device The cusp magnetic field configuration is obtained by two bundles of coaxial solenoids. Each bundle carries the same electric current but the directions of the current are opposite. The solenoids are powered by a single power supply (60 kw, 1200 A). The main characteristics of the magnetic system are listed in Table I. All the coils are powered at a current intensity of 1000 A. TABLE I. Characteristics of the magnetic system Length between point cusps (PC) Line cusp (LC) radius Peak magnetic field at PC Peak magnetic field at LC 78 cm 19 cm 0.4 T 0.25 T The vacuum vessel is a customized cusp geometry stainless steel AISI 304L. The main disk-shaped chamber has an inner diameter of 550 mm and is 70 mm wide. The plasma source is fed with gas through a mass flow controller (FC in Fig.4.2.1) that maintains a discharge pressure from 10-3 to 10-2 Pa. Vacuum pumping is provided by turbomolecular pumps (TPs) located at the line cusp (two 60 L/s) and at the out-point cusp (230 L/s). In order to monitor the concentration of neutral particles at the line and out-point cusp, two 40 IFP Activity Report

41 residual gas analyzer (QMS1 and QMS2) have been used, with independent differential pumping systems. The plasma is generated by a microwave beam at 2.45 Ghz, fed into the vacuum chamber through a rectangular quartz window situated near the in-point cusp, where the magnetic field reaches a maximum value. The beam propagates through a decreasing magnetic field until it is absorbed at the electron cyclotron resonant (ECR) magnetic field (87.5 mt) approximately situated at 3 cm with respect to the center of the cusp magnetic field (with 1000 A of current in each coil). The power deliverable by the microwave system is up to 3 kw. A Langmuir Probe (LP) has been used to determine the electron temperature (T e ) and the density (n e ). The LP is mounted through a vacuum flange at the line cusp and can be swept radially along the line cusp plane thanks to a remotely controlled linear motion drive. A typical profile of n e and T e is shown in Fig V) e e( Electron temperature T ECR zone electron temperature electron density Radially distance from the center (cm) 2) 10-3 (cm 10 /10 e Electron density n Fig Electron temperature and density profiles taken with the ECR plasma source at the line cusp plane Some technological experiments on the cusp plasma device have been carried out, in particular to investigate the dissociation of methane in a plasma environment and its conversion to hydrogen, and on the effects of dust on plasma fluctuation spectra. The main goals of the future experiments we planned are: 1) to achieve an high-ionized plasma (close to 100%); 2) to apply a rf electric field at the line cusp plasma by means of the two ring shaped electrodes, at a frequency close to the ion cyclotron frequency. The plasma so produced will allow studies of ponderomotive force effects as well as ion plugging and ion species separation. These investigations are of interest to fusion technology as a basis to process and separate the impurities coming from the exhaust gas that is pumped out from the vacuum vessel of a tokamak like ITER. 4.3 Measurements of fluctuations spectra in a Carbon dusty plasma Studies of the effects of the presence of dusts in plasmas are mainly related to two different branches of science: astrophysics and nuclear fusion. Dust is something common in the space environment. As far as nuclear fusion is concerned, it is expected that dust produced by the erosion of the material walls will be present in the region of the scrape off layer (SOL). The presence of charged dust particles can change the amplitude and the spectrum of the plasma fluctuations due to the dissipative effects of the charging collisions of plasma particles with dust, which produce fluctuations of the dust charge. The discreteness of the dust particles also induces plasma fluctuations different from the usual thermal fluctuations associated to the discreteness of electrons and ions. The relative importance of the two processes depends on the dust-charge density. Measurements of the plasma density and of IFP Activity Report

42 the potential fluctuations in selected parts of the spectrum in the presence of dust therefore can be used as a diagnostic of the main properties of the dust. An experimental campaign has been carried out using the cusp plasma device Omega operating at IFP to study the effects of dusts on the plasma characteristics. The cusp device is a favorable setup to this purpose because it confines a quiescent and unmagnetized plasma (in the central zone of the magnetic cusp configuration) at low neutral pressure, occupying a large volume. To be as close as possible to the actual conditions of the SOL region of tokamaks, carbon dusty particles have been produced by methane dissociation in an Argon-Methane discharge. Different concentrations of Ar-CH 4 have been used. A set of experiments with Ar-NH 3 has been carried out in order to compare gas mixtures with similar molecular structures respectively without and with dusts. Fluctuation measurements have been performed by means of an electrostatic probe located in the center of the cusp geometry and biased at the ion saturation voltage. Typical spectra, obtained using different gas mixtures, are shown in Fig Fig Power spectra of the density fluctuations in Ar (red curve), mixture Ar+50 % NH3 (violet curve) and Ar+50 % CH4 (blue curves). The results show an increase of the intensity of the low frequency branch of the fluctuation spectrum with increasing dust density (i.e. at higher concentrations of methane). These results are in satisfactory agreement with theoretical previsions and look promising for the future development of a dusty plasma diagnostic. The experiment has been done in collaboration with the Max-Plank-Institut, Garching, Germany, the University Federico II, Naples, Italy, and the University of Molise, Italy. 4.4 Methane cracking and hydrogen production in Ar plasma at atmospheric pressure Hydrogen is one of the possible future energy carriers to replace fossil fuels. A main issue to be solved for this to become a reality is that hydrogen should be produced from clean and renewable resources. An IFP team, in cooperation with the Istituto per l Energetica e le Interfasi (IENI), is deeply interested in H 2 generation through the processes of methane plasma cracking. To this purpose, we have built a plasma reactor that works at atmospheric pressure using a low temperature plasma such as that produced by a dielectric barrier discharge (DBD). A DBD is a widespread technique to produce atmospheric-pressure non-thermal plasmas. To produce a large volume, uniform, non-thermal plasma we have built a cylindrical reactor (see Fig.4.4.1). powered by a high-voltage pulse generator (6 KV 30 KV) with pulse width of about 10 ns and repetition rate from 1 khz up to 100 khz. The main goals of the experiment are: - study and development of the DBD plasma reactor with evaluation of the discharge parameters; 42 IFP Activity Report

43 - study of methane and hydrocarbons cracking with a non-equilibrium pulsed nanosecond glow discharge at high pressure, to increase the efficiency and the hydrogen selectivity; - optimization of the cracking efficiency, the H2 selectivity and minimization of the energy consumption by different electrodes configurations; - study of the methane and hydrocarbons cracking with the addition of small amounts of water vapour, to test different plasma conditions; - evaluation of the effects of the addition of a magnetic field. If a stationary magnetic field is superimposed in the discharge region by means of solenoids, the electron transport properties are enhanced thanks to the increase of the electron free path, with consequent growth of the atomic-molecular reactions between electrons and gas particles; - development and testing of an adequate H2 permeable membrane geometry to increase the selectivity of hydrogen in the reaction volume. Pd-alloy membranes seems to be promising for this application because of their high permeation rate for hydrogen and negligible rate for other gases. The following diagnostics will be employed to measure the plasma and gas parameters and to monitor the methane cracking reactions: 1) optical emission spectroscopy (ES); 2) gas-chromatography, to understand the reaction dynamics; 3) scanning electron microscopy (SEM); 4) transmission electron microscopy (TEM), to study the morphology and structure of the produced hydrocarbon film or soot; 5) Langmuir probe. Fig Atmospheric pressure plasma reactor for dielectric barrier discharge. The program is supported by INTAS international project (Hydrogen Technology and Biomass Conversion for Energy Generation 2005 INTAS Ref. Nr ). Since April 2006 we are working in collaboration with the IENI - CNR, the Centre National de la Recherche Scientifique (CNRS), France - Moscow Institute of Physics and Technology, Russia the Institute for Structural Makrokinetics and Materials Science, Russia and the AllRussian Research Institute for Fire Protection, Russia. The coordinator of the project is Dr. Iskender Gökalp, Director of Laboratoire de Combustion et Systèmes Réactifs, CNRS, France. IFP Activity Report

44 4.5 Planning and objectives of a flexible plasma facility for scaled plasma experiments (GyM) In 2006 IFP has started the implementation of a modern experimental device aimed at performing specific scientific and technological investigations on plasmas of interest for the European fusion programme. The GyM machine is a linear magnetic trap where a low density plasma is produced and contained in a cylindrical vacuum chamber by means of an externally applied strong magnetic field produced with a coaxial set of 10 copper coils carrying an electric current up to 1 ka. It is aimed to produce fully ionized, collisionless plasmas with main parameters (plasma density, temperature, magnetic field) suitably scaled from large fusion devices (like JET and ITER) in such a way that experimental investigations of drift instabilities, and of the associated plasma transport properties, can be performed at the same values of certain relevant dimensionless parameters. The device can be used, with minor modifications of its magnetic configuration, also to study various technological plasma applications, with possible spin-off for multi-charged ion production for accelerators, ion implantation in solid matter, and other frontier fields. The experimental programme will be carried out in collaboration with the CRPP-EPFL, Lausanne (which provided on loan the magnetic field coils, three sections of the vacuum chamber, and the mechanical support structure), and IAP-RAS, Nizhny Novgorod. In large plasma confinement devices, several interrelated physical processes take place at the same time, which cannot be investigated individually by control and suppression of those processes which are detrimental. On the contrary, in an appropriately designed small device it is possible to drive, study and control a single instability and therefore to extract pieces of information about its scalings with few relevant dimensionless parameters. If such key parameters take values of the same order of magnitude as in large devices, although the dimensional physical parameters are very different, the validity of the results of the smallscale experiment can be extended, to a certrain extent, to larger devices. The case of the drift instabilities in a magnetized plasma is a pertinent example. They are mostly electrostatic and are caused by spatial gradients of the plasma density and temperature. Drift modes are believed to be responsible for the leakage of plasma energy from a tokamak plasma, and the presence of toroidal and poloidal plasma velocities can be stabilizing or destabilizing factors for these modes. In a tokamak discharge, radial gradients of toroidal and poloidal plasma velocities cannot be controlled separately. In addition the use of RF or of neutral beams injected to drive a toroidal rotation also induce a plasma heating, modifying T e /T i. The key parameters varying at the same time, it is very difficult to discern among their different roles. This kind of investigation can be performed in a relatively simple way in a small-scale plasma, provided each possible exciting and stabilizing mechanism, as for example T e /T i, the radial gradients of n i, T i, the longitudinal plasma flow, the azimuthal plasma flow, controlled while maintaining the other parameters almost fixed. Following these ideas, the construction of GyM, which is a flexible, multi-purpose, and easily diagnosable device, where lastgeneration radio-frequency (RF) sources (gyrotrons) will be used to produce, sustain and shaping the plasma, has begun. Following the criteria of scalability discussed above, typical physical parameters have been identified: n e cm -3, T e 30 ev, T i T e in low density regimes, B 1 5 kg. GyM will have a modular structure that will include a source region for plasma generation (A), the experimental region (C), and an intermediate transition region (B). A suitable differential pumping in the region B will be needed in order to remove all neutrals from region C, where the experimental investigation will be performed. The plasma expected to be produced in GyM can be easily diagnosed by probes of various kinds (Langmuir probes, plug probes, Mach probes, and gridded energy analyzers), which can be easily inserted into the plasma to give radial and axial profiles of the density, the temperature, the flows and the excited electrostatic fluctuations. In large-scale plasmas, like existing and future tokamaks, probes cannot be used except in the very peripheral region of the plasma column. In a dilute plasma they can give the spatial distributions of the main physical parameters with very good resolution. Ion energies and flows can be adequately 44 IFP Activity Report

45 measured by means of ion energy analyzers. The implementation of specific diagnostics for the excited waves, as reflectometry and probe techniques, is foreseen together with spectroscopic measurements for detecting ion flows. The circular magnetic field coils will be mounted on rails in order to have the possibility to change easily the relative position. In such a way, several magnetic configurations will be rmade available: classical magnetic mirror, end-cusp magnetic configuration, central magnetic cusp with variable width. In the early phase of the experimentation, the plasma will be produced and shaped by means of heated filaments and RF at 2.45 GHz. In a later phase, a gyrotron will be used, to apply RF at 28 GHz, power 15 kw, CW, to produce, sustain and shape the plasma-target. An essential part of the experimental programme will be the implementation of a plasma-target fully sustained by RF. A highly ionized plasma is expected under ECR conditions sustained in a linear trap by the gyrotron source. The plasma density in ECR discharges can be varied up to values close to the cut-off density (about cm -3 at 28 GHz) controlling the microwave power level and the gas injection rate. Being ionized inside the linear trap, the plasma will escape into the drift chamber along the magnetic field lines with the ion-acoustic velocity. The mean free path of a neutral before ionization will be rather small ( 1 mm), therefore the neutral flux from the source to the experimental chamber is expected to be also negligibly small. The plasma density profile will be adjusted placing the specially designed grids (diaphragms) at the input of the experimental chamber. Such grids can shape the radial density profile according to the radial distribution of the grid transparency. Control of the power deposition and the neutral gas injection rate will allow varying the electron temperature in a limited range. An additional control of the electron temperature profile can be possibly realized by varying the microwave intensity distribution across the quasi-optical beam and the localization of the EC absorption zone. The construction of the GyM device at IFP-CNR has started and the experimental programme to be carried out is under defintion. The machine will be a tool of IFP-CNR for testing new physical ideas and technological applications of RF produced plasmas, having the possibility of a careful control of plasma parameters. The scientific and technological programme of GyM will be open to external collaborations and proposals. IFP Activity Report

46 46 IFP Activity Report

47 5. Plasma-aided material processing 5.1 Plasma production of semiconducting and conducting polymers Polymers are used in a large number of applications because of their several advantages. For applications requiring optical and conductive properties, the choice of a suitable polymer is limited to polymers with a conjugated chemical structure such as polyacetylene, polypyrrole, and polythiophene. Very thin film of polythiophene can be deposited by electrochemical procedures. Plasma polymerization can be an alternative to more conventional methods. In this project we have produced thiophene-like films using a pulsed plasma. Their structural and optical properties have been investigated by varying the RF peak powers. The energy gap decreased from 2.69eV to 1.86eV with increasing RF plasma power. These thin films also showed semiconductive polymers characteristics. The infrared spectra of the plasma polymerized films obtained using alkylthiophene as monomer, pointed out characteristic bands at around 3098 cm -1, 780 cm -1 and 700 cm -1, showing that the thiophene ring is mostly preserved during plasma polymerization. However, the disappearance of some absorption bands indicates that partial fragmentation of monomer occurs, as confirmed also by XPS analysis. Fig shows the UV-visible absorption spectra of plasma polymerized films based on alkylthiophene. The absorption band around 320 nm that is clearly visible shifts at greater wavelengths with increasing RF power, in which conditions broadening of the absorption band is also detected. As well-known, the power increase enhances both the fragmentation in the plasma phase and the ion bombardment on the growing film. This can produce more branching and a crosslinking reaction inside the film, giving rise to a denser film, and a π- electron delocalization in wide band states, with a reduction in the band gap. 4,5 4 3,5 Absorbance 3 2,5 2 1,5 50 W 120 W 100 W Fig Absorption spectra 1 0,5 30 W Wavelength (nm) Semiconductive polymers produced by plasma deposition exhibit novel properties not available in other materials. These polymers can be used in a large number of applications including Organic Light Emitting Diodes (OLEDs), antistatic materials, corrosion protection, smart windows and photodetectors. 5.2 Plasma treatment of biodeteriorated ancient papers The deterioration of paper materials is mainly due to the degradation of cellulose caused by several factors, such as chemical attack due to acidic hydrolysis, oxidative agent, light, air pollution and biological attack due to microorganisms like bacteria and fungi. Various technologies exist to limit the degradation of the paper materials but only in a few cases they IFP Activity Report

48 produce good results. Plasma technology is an innovative process alternative to the conventional methods. The plasma treatment produces synergetic results of biological agent sterilization, strengthening and conservation of the paper, is environmentally friendly and can be used for industrial applications. The already achieved results can be summarized as foillows: a)enhancement of mechanical properties After plasma treatments the mechanical properties of ancient and Whatman paper were determined by tensile strength measurements. Whatman paper was utilized as a reference substrate. The tensile strength was evaluated by stress-strain curves for both paper, with the maximum strength of the paper corresponding to the point where the paper fibres break. Ar/H 2, O 2 /H 2, Ar/O 2 and vaporized hexamethyldisiloxane mixtures were tested. The tensile strength measured for ancient and Whatman paper after plasma treatment was found enhanced in both samples. 20 ancient paper whatman paper Tensile strength (Mpa) Fig Tensile strenghth 10 untreated Ar/H2 mixture O2/H2 mixture With SiOx film b) Paper conservation by means of plasma treatment The restoration process does not preserve the paper for the future since it will be still subject to the various degradation factors (chemical, physical and microbiological). To prevent this a plasma treatment was considered and tested, such as to produce an optically transparent layer of few nanometres of thickness on the paper surface. The layer was produced using the hexamethyldisiloxane as monomer source. The deposited layer actually confers to the paper surface a high chemical stability, a low permeability to the aeriforms and water repellent property. Figs 5.2.2a and 5.2.2b show the morphological structure of the paper fibres before and after the plasma treatment. The fibres treated with the plasma are completely covered by a silicon-like film. The morphology exhibited in Fig.5.2.2b is characteristic of amorphous films with irregular growth of deposit islands. Before deposition After deposition Fig.5.2.2a - AFM analysis 1x1 µm 2 Fig.5.2.2b - AFM analysis 1x1 µm 2 48 IFP Activity Report

49 5.3 Plasma treatment of Polymeric Composite Materials for Industrial application (patent No.: MI2006A002482) It is well known that Polymeric Composite Materials (PCMs) provide desirable properties such as stiffness and lightness. However their application is in many cases limited due to the water vapour absorption. The recent progresses in plasma technology now allow to produce PCMs with advanced performance characteristics. In this patented work, we have developed a plasma process to produce a thin film enhancing the functional properties of the PCM surface. In particular, the thin film provides a water vapour barrier and water repellent properties to the material. 5.4 Surface analysis of plasma exposed tokamak tiles (ERCAR task) The program TW4-TPP-ERCAR was started following the results obtained in plasma simulator facilities, such as PISCES-B, in which carbon based materials exposed to dose exceeding10 26 m -2 revealed a drastic change in their surface morphology. The formation of a grass-like structure accompanied by a large increase of the surface area depicted an erosion scenario totally unacceptable for the ITER divertor. Indeed, the deterioration of the lifetime, the material transport, and the total tritium inventory would rule out the usa of these material as PFC. The purpose of the Task TW4-TPP-ERCAR was to study the morphology of plasma facing component exposed to large fluence in tokamaks, with particular focus on the erosion zones. Five samples, belonging to the same graphite tile, retrieved from the toroidal belt limiter of TEXTOR, were studied. Of the five samples, three are representative of the erosion dominated zone, the fourth comes were the deposition regime starts to set on, and the fifth is from the net deposition zone. A further sample was cut out from the opposite surface and used as reference virgin material. The morphology of the samples was investigated by Scanning Electron Microscopy and their surface composition by ESD analysis. None of the erosion-dominated samples revealed a grass-like structure on the surface. However, their morphology differs from that of the reference sample and craters of 5mm size are always present. Both arcing and electron bombardment can be the cause. Silicon is still strongly present, as well as traces of the metals of the main chamber. The deposition dominated zone preserves the morphology of the reference sample. 5.5 Highly absorptive ceramic coatings for high power microwaves in the mmwaves range (patent No. PCT/EP2006/050605) Due to the increasing interest in high power, high frequency millimeter-wave gyrotrons, measurements of the gyrotron power and energy become important because they allow accurate energy balance in ECRH during plasma heating. The expected increase in power, up to 2 MW, and in time, up to 10 s (quasi continuous wave) now calls for new technological solutions in manufacturing bolometric loads, particularly in making available absorbing layer ceramics particularly resistant to thermal shocks. In this particular case, also a good absorption capability at 140 GHz is also requested. In a previous work we studied alumina based coatings with various techniques, such as Environmental Scanning Electron Microscopy (ESEM), micro-analysis with X-ray EDS, Differential Scanning Calorimeter (DSC), X-ray diffraction analysis (XRD). There it was shown that repeated exposures to high energy fluxes can caus degradation of the coating. In order to select an absorbing ceramic coating to be deposited on the inner surface of the load, characterization of many materials was performed with respect to their absorbing IFP Activity Report

50 capability at the frequency of interest (140 Ghz), thermal shock and fatigue resistance caused by long-term exposure to high power mm-wave radiation. Three coating materials (B 4 C, Cr 2 O 3 and ZrO 2 ), with absorption capabilities for microwave radiation in the range of GHz as good as those of Al 2 O 3-13TiO 2, were found to exhibit good characteristics in terms of heat resistance (see Table) and, in the case of Cr 2 O 3, also in terms of thermal diffusivity. The coatings obtained with the APS technique are open to further improvements in terms of thermal conductivity using VPS. This technique should reduce the open porosities, thus providing better adhesion and density which are the key issues to rise the maximum thermal flux for fixed surface temperature. The B 4 C (see Fig.5.6.1) has better resistance to the temperature and shows an improved microwave absorption compared with other coatings. Heat Load Heat Load Heat Load Table: Thermal conductivity at four different power densities Coatings Heat Load 100 W/cm W/cm W/cm W/cm 2 Therm. cond.. (W/m. C) Therm. cond.. (W/m. C) Therm. cond.. (W/m. C) Therm. cond.. (W/m. C) B 4 C Cr 2 O Al 2 O 3-13TiO ZrO2 VPS ZrO2 APS The utilization of B 4 C as absorbing coating layer in the inner wall of the bolometric device has been patented (Italian Patent No. MI2005A International Patent Application No. PCT/EP2006/ filed on 1 st February 2006). Fig B 4 C coating layer cross-section of an exposed sample 50 IFP Activity Report

51 6. Patents Title: Bolometric device with receiving cavity for measuring the power of a beam of high frequency microwaves and process for coating the internal surface of said cavity Presented by N. Spinicchia, A. Bruschi, S. G. Cirant, V. Muzzini and A. Nardone International Patent Application No. PCT/EP2006/050605, filed Beholders: CNR Title: Rivestimento ibrido idrorepellente e impermeabile all umidità per materiali compositi polimerici rinforzati deposto mediante Plasma Enhanced Chemical Vapour Deposition Presented by F. Taddei, A. Cremona and E. Vassallo, Italian Patent No. MI2006A , filed 22/12/2006 Beholders: F. Taddei, A. Cremona and E. Vassallo, IFP Activity Report

52 52 IFP Activity Report

53 7. European Contracts Contract Ref & No. Signature date End date Principal Investigator EFDA/ Sozzi FU06-CT EFDA/ Bruschi EFDA/ Sozzi EFDA/ Simonetto FU06-CT EFDA/ Ramponi FU06-CT EFDA/ Simonetto FU06-CT JW4-OEP-ENEA-42B Cirant/Sozzi FU06-CT JW5-OEP-ENEA Gorini FU06-CT JW6-OEP-ENEA Gorini FU06-CT TCP Cirant FU06-CT TW4-TPP-TARCAR Ghezzi TCN IFP Activity Report

54 TW5-THHE-CCGDS Cirant TCN TW6-THHE-CCGDS Cirant TCN TW6-THHE-ECHULA Cirant/Ramponi TCN TW6-THHE-CCGT Cirant TCN TW6-TPDS-DIADEV Gorini 8. Industrial Contracts Company Signature date End date Principal Investigator Luxottica Vassallo Ecopack Vassallo Ecotec Gestione Impianti Bonizzoni Eldor Corporation Vassallo Fondazione Cariplo Bonizzoni 54 IFP Activity Report

55 9. Publications Refereed publications 2005 Jacchia A., De Luca F., Ryter F., Bruschi A., Leuterer F., Neu R., Pereverzev G., Suttrop W., Wagner D. and ASDEX Upgrade Team - Nonlinear pertubative electron heat transport study in the ASDEX Upgrade tokamak - Nuclear Fusion 45, (2005) Cremona A., Laguardia L., Vassallo E., Ambrosone G., Coscia U., Orsini F. and Poletti G. -Optical and structural properties of siliconlike films prepared by plasma-enhanced chemical-vapor deposition - J. Applied Physics 97, (2005) Minardi E. - The magnetic entropy concept - J. Plasma Physics 71, (2005) Bobrova N.A., Lazzaro E. and Sasarov P.V. - Magnetohydrodynamic two-temperature equations for multicomponent plasma - Physics of Plasmas 12, (2005) Borgogno D., Grasso D., Porcelli F., Califano F., Pegoraro F. and Farina D. - Aspects of threedimensional magnetic reconnection - Physics of Plasmas 12, (2005) Weisen H., Zabolotsky A., Angioni C., Furno I., Garbet X., Giroud C., Leggate H., Mantica P., Mazon D., Weiland J., Zabeo L., Zastrow K.-D. and the JET EFDA Contributors - Collisionality and shear dependence of density peaking in JET and extrapolation to ITER - Nuclear Fusion 45, L1-L4 (2005) Weiland J., Asp E., Garbet X., Mantica P., Parail V., Thomas P., Suttrop W., Tala P. and the JET EFDA Contributors - Effects of temperature ratio on JET transport in hot ion and hot electron regimes - Plasma Phys. Control. Fusion 47, (2005) Asp E., Weiland J., Garbet X., Mantica P., Parail V., Suttrop W. and the JET EFDA Contributors - JETTO simulations of T e /T i effects on plasma confinement - Plasma Phys. Control. Fusion 47, (2005) Farina D. and Bulanov S.V. - Dynamics of relativistic solitons - Plasma Phys. Control. Fusion 47, A73-A80 (2005) D'Arcangelo O., Garavaglia S., Simonetto A., Sozzi C., Bersanelli M., Mennella A., Villa F. - Measurements of Beam Pattern Perturbation in Corrugated Feed Horn Arrays for CMB Observations - Experimental Astronomy 16, (2005) Figueiredo N., Bersanelli M., Childers J., D'Arcangelo O., Halevi D., Janssen M., Kedward K., Lemaster N., Lubin P., Mandolesi N., Marvil J., Meinhold P., Mejia J., Mennella A., Natoli P., O'Neil H., Pina A., Pryor M., Sandri M., Simonetto A., Sozzi C., Tello C., Villa F., Villela T., Williams B., Wuensche C. - The Optical Design of the Background Emission Anisotropy Scanning Telescope (BEAST) - The Astrophysical Journal Supplement Series, 158, , (2005) Voitsekhovitch I., Garbet X., McDonald D. C., Zastrow K.-D., Adams M., Baranov Yu., Belo P., Bertalot L., Budny R., Conroy S., Cordey J. G., Garzotti L.,Ã Â Mantica P., McCune D., Ongena J., Parail V., Popovichev S., Stork D., Whiteford A.D., and JET EFDA contributors - Density dependence of trace tritium transport in H-mode Joint European Torus plasma - Phys. Plasmas 12, (2005) Houlberg W. A., Gormezano C., Artaud J. F., Barbato E., Basiuk V., Becoulet A., Bonoli P., Budny R. V., Eriksson L. G., Farina D., Gribov Yu., Harvey R. W., Hobirk J., Imbeaux F., Kessel C. E., Leonov V., Murakami M., Polevoi A., Poli E., Prater R., John H. St., Volpe F., Westerhof E., Zvonkov A., ITPA Steady State Operation Topical Group and ITPA Confinement Database and Modeling Topical Group IFP Activity Report

56 - Integrated modelling of the current profile in steady-state and hybrid ITER scenarios - Nucl. Fusion 45, (2005) Berrino J., Lazzaro E., Cirant S., D'Antona G., Gandini F., Minardi E. and Granucci G. - Electron cyclotron emission temperature fluctuations associated with magnetic islands and real-time identification and control system - Nucl. Fusion 45, , (2005) Mantica P., Thyagaraja A., Weiland J., Hogeweij G. M. D., Knight P. J. - Heat pinches in electronheated tokamak plasmas: theoretical turbulence models versus experiments - Phys.Rev.Letters 95, , (2005) Bruschi A., Cirant S., Gandini F., Gittini G., Granucci G., Mellera V., Muzzini V., Nardone A., Simonetto A., Sozzi C., Spinicchia N., Angella G., Signorelli E. - Development of CW and shortpulse calorimetric loads for high power millimeter-wave beams - Fusion Engineering and Design 74, (2005) Verhoeven A.G.A., Bongers W.A., Bruschi A., Cirant S., Elzendoorn B.S.Q., Gatenbein G., Graswinckel M.F., Heidinger R., Kasparek W., Kruyt O.G., Lamers B., Piosczyk B., Plaum B., Ronden D.M.S., Saibene G., Stuivinga M. and Zohm H. Design of the mm-wave system of the ITER ECRH upper launcher - Fusion Engineering and Design 74, (2005) Ronden D.M.S., Bruschi A., Danilov I., Elzendoorn B.S.Q., Graswinckel M.F., Heidinger R., Ramponi G., and Verhoeven A.G.A. Digital mock-up design of the remote steerable ITER ECRH launching system - Fusion Engineering and Design 74, (2005) Cupido L., De La Luna E., Antonucci C., Guigon A., van Amerongen F.J., Bongers W.A., Donnè A.J.H., Graswinckel M.F., Bruschi A., Cirant S., Simonetto A., Sozzi C., Wagner D., Manso E., Meneses L., Silva F., Varela P., Balshaw N., Chareau J.M., Conway G., Fessey J., Hanks S., Pearce R., Ricardo V., Sands D., Starky D., Tisconia T., JET-EFDA Contributors - New millimeter-wave access for JET reflectometry and ECE - Fusion Engineering and Design 74, (2005) Weber S., Lontano M., Passoni, M., Riconda C., Tikhonchuk V.T. - Electromagnetic solitons produced by stimulated Brillouin pulsations in plasmas - Physics of Plasmas 12, (2005) Minardi E. - Thermodynamics of reactive marginal instabilities - Journal of Plasma Physics 71, 753, (2005) Simonetto A., D'Arcangelo O., Figini L. - Effect of Cable Length in Vector Measurements of Very Long Millimeter-Wave Components - IEEE Transactions on Microwave Theory and Techniques 53, (2005) Bruschi A., Cirant S., Moro A., Platania P., Sozzi C. - Advanced Optics for the Remote Steering ITER ECRH Upper Launcher - Journal of Physics Conference Series 25, (2005) Cirant S., Berrino J., Gandini F., Granucci G., Iannone F., Lazzaro E., D Antona G., Farina D., Koppenburg K., Nowak S., Ramponi G. - Crucial issues of multi-beam feed-back control in fusion plasmas - Journal of Physics Conference Series 25, (2005) Ramponi G., Farina D. and Nowak S. - Capabilities of the ITER ECRH Upper Launcher at low magnetic fields - Journal of Physics Conference Series 25, (2005) Sozzi C., Granucci G., Nowak S., Bruschi A., Farina D., Gandini F., Panaccione L., Pericoli-Ridolfini V., Angelini B., Annibaldi S. V., Apicella M. L., Apruzzese G., Barbato E., Buratti P., Calabr G., Castaldo C., Cirant S., De Benedetti M., Berrino J., Bertocchi A., Cardinali A., Carraro L., Centioli C, Cesario R., Cocilovo V., Crisanti F., DeAngelis R., De Marco F., Esposito B., Frigione D., Gabellieri L., Giovannozzi E., Iannone F., Kroegler H., Lazzaro E., Leigheb M., Marinucci M., Marocco D., Mazzitelli G., Mazzotta C., Mirizzi F., Monari G., Orsitto F., Pacella D., Panella M., Pieroni L., Podda S., Puiatti M. E., Ravera G., Regnoli G., Righetti G. B., Romanelli F., Romanelli M., Simonetto A., Smeulders P., Sternini E., Tilia B., Tudisco O., Tuccillo A., Vitale V., Vlad G., Zonca F. - ITB formation with counter 56 IFP Activity Report

57 ECCD and LHCD and Suprathermal ECCD experiments on FTU in ITER relevant conditions - Journal of Physics Conference Series 25, (2005) Henderson M., Chavan R., Nikkola P., Ramponi G., Saibene G., Sanchez F., Sauter O., Shidara H., Zohm H. - The Physics performance of the Front Steering Launcher for the ITER ECRH Upper Port - Journal of Physics Conference Series 25, (2005) Zohm H., Heidinger R., Henderson M., Poli E., Ramponi G., Saibene G., Verhoeven A.G.A. - Comparison of the performance of different options for ITER ECRH Upper Launcher - Journal of Physics Conference Series 25, (2005) Alberti S., Arnoux G., Porte L., Bortolon A., Karpushov A., Martin Y., Nowak S., Pitts R. and the TCV Team - Third-harmonic X-mode, real-time controlled top-launch ECW experiments on TCV Tokamak - Journal of Physics Conference Series 25, (2005) Califano F., Lontano M. - Electron Hole Generation and Propagation in a Inhomogeneous Collisionless Plasma - Phys. Rev.Letters 95, (2005) Sozzi C., Bruschi A., Simonetto A., De La Luna E., Fessey J., Riccardo V. and JET-EFDA Contributors - Optical design of the oblique ECE antenna system for JET - Fusion Engineering and Design 74, 691 (2005) Angelini B., Annibaldi S.V., Apicella M.L., Apruzzese G., Barbato E., Bertocchi A., Bombarda F., Bourdelle C., Bruschi A., Buratti P., CalabrÃ_ G., Cardinali A., Carraro L., Castaldo C., Centioli C., Cesario R., Cirant S., Cocilovo V., Crisanti F., De Angelis R., De Benedetti M., De Marco F., Esposito B., Frigione D., Gabellieri L., Gandini F., Garzotti L., Giovannozzi E., Gormezano C., Gravanti F., Granucci G., Hoang G.T., Iannone F., Kroegler H., Lazzaro E., Leigheb M., Maddaluno G., Maffia G., Marinucci M., Marocco D., Martin-Solis J.R., Martini F., Mattioli M., Mazzitelli G., Mazzotta C., Mirizzi F., Monari G., Nowak S., Orsitto F., Pacella D., Panaccione L., Panella M., Papitto P., Pericoli- Ridolfini V., Pieroni L., Podda S., Puiatti M.E., Ravera G., Regnoli G., Righetti G.B., Romanelli F., Romanelli M., Santini F., Sassi M., Saviliev A., Scarin P., Simonetto A., Smeulders P., Sternini E., Sozzi C., Tartoni N., Terranova D., Tilia B., Tuccillo A.A., Tudisco O., Valisa M., Vershkov V., Vitale V., Vlad G. and Zonca F. - Overview of the FTU results - Nucl. Fusion 45, S227-S238, (2005) C. Marchetto, F. Califano, M. Lontano - Turbulence healing via plasma-wave interaction: the results of a study via kinetic codes - Computer Physics Communications 169, , (2005) Bardi U., Chenakin S. P., Ghezzi F., Giolli C., Goruppa A., Lavacchi A., Miorin E., Pagura C., Tolstogouzov A. - Higth-temperature oxidation of CrN/A1N multilayer coatings - Applied Surface Science 252, (2005) Alberti S., Arnoux G., Porte L., Hogge J.-P., Marletaz B., Marmillod P., Martin Y., Nowak S. and TCV Team - Third-harmonic,top-launch,ECRH experiments on TCV tokamak - Nucl. Fusion 45, 1224 (2005) Mejia J., Bersanelli M., Burigana C., Childers J., Figuereido N., Kanga M., Lubin P., Maino D., Mandolesi N., Marvil J., Meinhold P., O'Dwyer I., O'Neill H., Platania P., Seiffert M., Stebor N., Tello C., Villela T., Wandelt B. and Wuensche C.A. - Galactic Foreground Contribution to the BEAST Cosmic Microwave Background Anisotropy Maps - Astrophys. Jour. Suppl. Series 158-1, (2005) Laguardia L., Vassallo E., Cappitelli F., Mesto E., Cremona A., Sorlini C., Bonizzoni G. - Investigation of the effects of plasma treatments on biodeteriorated ancient paper - Applied Surface Science, 252/4, (2005) Spinicchia N., Angella G., Benocci R., Bruschi A., Cremona A., Gittini G., Nardone A., Signorelli E., Vassallo E. - Study of plasma sprayed ceramic coatings for high density power microwave loads - Surf. Coat. Technol., 200/1-4, 1151 (2005) IFP Activity Report

58 Giacomelli L., Conroy S., Ericsson G., Gorini G., Henriksson H., Hjalmarsson A., Källne J. and Tardocchi M. - Comparison of neutron emission spectra for D and DT plasmas with auxiliary heating - The European Physical Journal D, 33, 235 (2005) Henriksson H., Conroy S., Ericsson G., Giacomelli L., Gorini G., Hjalmarsson A., Kaellne J., Tardocchi M. and M. Weiszflog - Systematic spectral features in the neutron emission from NB heated JET DT plasmas - Plasma Phys. Controlled Fusion, 47, 1763 (2005) Murari A., Bertalot L., Bonheure G., Conroy S., Ericsson G., Kiptily V., Lawson K., Popovichev S., Tardocchi M., Afanasyiev V., Angelone M., Fasoli A., Kaellne J., Mironov M., Mlynar J., Testa D., Zastrow K. D. and JET-EFDA Contributors - Burning plasma diagnostics for the physics of JET and ITER - Plasma Phys. Controlled Fusion, 47, B249 (2005) Giacomelli L., Hjalmarsson A., Sjöstrand H., Glasser W., Källne J., Conroy S., Ericsson G., Gatu Johnson M., Gorini G., Henriksson H., Popovichev S., Ronchi E., Sousa J., Sundén Andersson E., Tardocchi M., Thun J., Weiszflog M. and contributors to the JET-EFDA work program - Advanced neutron diagnostics for ITER fusion experiments - Nucl. Fusion, 45, 1191 (2005) Hogge J. P., Alberti S., Arnold A., Bariou D., Benin P., Bonicelli T., Bruschi A., Chavan R., Cirant S., Dumbrajs O., Fasel D., Gandini F., Giguet E., Goodman T., Heidinger R., Henderson M., Illy S., Jin J., Lievin C., Magne R., Marmillod P., Mondino P.-L., Perez A., Piosczyk B., Porte L., Rzesnicki T., Santinelli M., Thumm M., Tran M.Q., Yovchev I. - Development of a 2-MW, CW Coaxial Gyrotron at 170 GHz and Test Facility for ITER - Journal of Physics Conf. Series, 25, 33-44, (2005) Plaum B., Gantenbein G., Kasparek W., Schwörer K., Grünert M., Braune H., Erckmann V., Hollmann F., Jonitz L., Laqua H., Michel G., Noke F., Purps F., Bruschi A., Cirant S., Gandini F., Verhoeven A.G.A., ECRH groups at IPP Greifswald, FZK Karlsruhe and IPF Stuttgart - High-power tests of a remote steering launcher mock-up at 140 Ghz - Journal of Physics Conf. Series, 25, , (2005) Pericoli-Ridolfini V., Barbato E., Buratti P., Calabrò G., Castaldo C., De Benedetti M., Esposito B., Gabellieri L., Gormezano C., Granucci G., Leigheb M., Marinucci M., Marocco D., Mazzotta C., Mirizzi F., Nowak S., Panaccione L., Regnoli G., Romanelli M., Smeulders P., Sozzi C., Tudisco O., Tuccillo A. A., Angelini B., Annibaldi S. V., Apicella M. L., Apruzzese G., Bertocchi A., Bruschi A., Cardinali A., Carraro L., Centioli C., Cesario R., Cirant S., Cocilovo V., Crisanti F., De Angelis R., De Marco F., Frigione D., Gandini F., Giovannozzi E., Iannone F., Kroegler H., Lazzaro E., Maddaluno G., Mazzitelli G., Monari G., Orsitto F., Pacella D., Panella M., Pieroni L., Podda S., Puiatti M. E., Ravera G., Righetti G. B., Romanelli F., Simonetto A., Sternini E., Tilia B., Vitale V., Vlad G. and Zonca F. - High density internal transport barriers for burning plasma operation - Plasma Phys. Control. Fusion, 47, B285 B301, (2005) 2006 H. Sjostrand, L. Giacomelli, E. Andersson Sunden, S. Conroy, G. Ericsson, M. Gatu Johnson, C. Hellesen, A. Hjalmarsson, J. Kallne, E. Ronchi, M. Weiszflog, G. Wikstrom, G. Gorini, M. Tardocchi, A. Murari, G. Kaveney, S. Popovichev, J. vsousa, R. C. Pereira, A. Combo, N. Cruz and JET EFDA contributors - New MPRu Instrument for Neutron Emission Spectroscopy at JET - Rev. Sci. Instr., 77, 10E717 (2006) L. Giacomelli, E. Andersson Sunden, S. Conroy, G. Ericsson, M. Gatu Johnson, C. Hellesen, A. Hjalmarsson, J. Kaellne, E. Ronchi, H. Sjoestrand, M. Weiszflog, G. Gorini, M. Tardocchi, A. Murari, S. Popovichev, J. Sousa, R.C. Pereira, A. Combo, N. Cruz and JET EFDA contributors - Development and Characterization of the Proton Recoil Detector for the MPRu Neutron Spectrometer - Rev. Sci. Instr., 77, 10E708 (2006) M. Gatu Johnson, L. Giacomelli, A. Hjalmarsson, M. Weiszflog, E. Andersson Sunden, S. Conroy, G. Ericsson, C. Hellesen, J. Kaellne, E. Ronchi, H. Sjoestrand, G. Gorini, M. Tardocchi, A. Murari, S. Popovichev, J. Sousa, R. C. Pereira, A. Combo, N. Cruz and JET EFDA contributors - The TOFOR Neutron Spectrometer and its First Use at JET - Rev. Sci. Instr., 77, 10E702 (2006) 58 IFP Activity Report

59 M. Tardocchi, G. Gorini, E. Andersson Sundén, S. Conroy, G. Ericsson, M. Gatu Johnson, L. Giacomelli, C. Hellesen, A. Hjalmarsson, J. Källne, E. Ronchi, H. Sjöstrand, M. Weiszflog, T. Johnson, P. U. Lamalle and JET EFDA contributors - Modeling of neutron emission spectroscopy in JET discharges with fast tritons from (T) D ion cyclotron heating - Rev. Sci. Instr., 77, (2006) E. Lazzaro, E. Joffrin, R. Coelho, P. Mantica, A. I. Smolyakov, P. Zanca, G. Gervasini and M. C. Varischetti - Effect of electrodynamic braking force localized on rational surfaces - Phys. Scripta. 73, (2006) A. A. Tuccillo, F. Crisanti, X. Litaudon, Yu. F. Baranov, A. Becoulet, M. Becoulet, L. Bertalot, C. Castaldo, C.D. Challis, R. Cesario, M. R. De Baar, P. C. de Vries, B. Esposito, D. Frigione, L. Garzotti, E. Giovannozzi, C. Giroud, G. Gorini, C. Gormezano, N. C. Hawkes, J. Hobirk, F. Imbeaux, E. Joffrin, P. J. Lomas, J. Mailloux, P. Mantica, M. J. Mantsinen, D. Mazon, D. Moreau, A. Murari, V. Pericoli-Ridolfini, F. Rimini, A. C. C. Sips, C. Sozzi, O. Tudisco, D. Van Eester, K-D. Zastrow and JET- EFDA work-programme contributors - Development on JET of advanced tokamak operations for ITER - Nucl. Fusion 46, , (2006) M. Lontano, M. Passoni, C. Riconda, V.T. Tikhonchuk, S. Weber - Electromagnetic solitary waves in the saturation regime of stimulated Brillouin backscattering - Laser and Particle Beams 24, , (2006) P. Mantica, D. Van Eester, X. Garbet, F. Imbeaux, L. Laborde, M. Mantsinen, A. Marinoni, D. Mazon, D. Moreau, N. Hawkes, E. Joffrin, V. Kiptily, S. Pinches, A. Salmi, S. Sharapov, A. Thyagaraja, I. Voitsekhovitch, P. de Vries, and K.-D. Zastrow - Probing Internal Transport Barriers with Heat Pulses in JET - Physical Review Letters 96, (2006) P. Mantica, F. Ryter, C. Capuano, H. U. Fahrbach, F. Leuterer, W. Suttrop, J. Weiland and ASDEX- Upgrade Team - Investigation of electron heat pinch in ASDEX-Upgrade - Plasma Phys. Control. Fusion 48, , (2006) L. Garzotti, X. Garbet, A. Thyagaraja, M. R. de Baar, D. Frigione, P. Mantica, V. Parail, B. Pegourie, L. Zabeo and JET EFDA contributors - Simulations of JET pellet fuelled ITB plasmas - Nucl. Fusion 46, 73-81, (2006) E. Vassallo, A. Cremona, L. Laguardia and E. Mesto - Preparation of plasma-polymerized SiOxlike thin films from a mixture of hexamethyldisiloxane and oxygen to improve the corrosion behaviour - Surf. Coat. Technol. 200/9 3035, (2006) M. Lontano, M. Passoni - Electrostatic field distribution at the sharp interface between high density matter and vacuum - Physics of Plasmas 13, , (2006) J. Berrino, S. Cirant, F. Gandini, G. Granucci, E. Lazzaro, F. Jannone, P. Smeulders and G. D'Antona - Automatic Real-time Tracking and Stabilization of Magnetic Islands in a Tokamak using Temperature Fluctuations and ECW Power - IEEE Transactions of Nuclear Science 53, No. 3, (2006) N. Spinicchia, G. Angella, M. De Angeli, G. Gervasini, Signorelli E. - Growth of thin films and hydrogen production in a cusp plasma device - Surface & Coatings Technology 200, , (2006) M. Passoni, M. Lontano, C. Riconda, V. T. Tikhonchuk, S. Weber and A. Ghizzo - Electromagnetic droplets created by stimulated Brillouin backscattering - J. Phys. IV France 133, , (2006) E. Vassallo, L. Laguardia, D. Ricci, G. Bonizzoni - Innovative Plasma Processes for Consolidation of Biodeteriorated Ancient Papers - Macromolecular Symposia 238, 46-51, (2006) M. E. Puiatti, M. Valisa, C. Angioni, L. Garzotti, P. Mantica, M. Mattioli, L. Carraro, I. Coffey, C. Sozzi and JET-EFDA contributors - Analysis of metallic impurity density profiles in low collisionality Joint European Torus H-mode and L-mode plasmas - Physics of Plasmas 13, , (2006) IFP Activity Report

60 A. Marinoni, P. Mantica, D. Van Eester, F. Imbeaux, M. Mantsinen, N. Hawkes, E. Joffrin, V. Kiptily, S. D. Pinches, A. Salmi, S. Sharapov, I. Voitsekhovitch, P. de Vries, K. D. Zastrow and JET-EFDA contributors - Analysis and modelling of power modulation experiments in JET plasmas with internal transport barriers - Plasma Phys. Control. Fusion 48, , (2006) E. Vassallo, A. Cremona, F. Ghezzi, F. Dell'Era, L. Laguardia, G. Ambrosone and U. Coscia - Structural and optical properties of amorphous hydrogenated silicon carbonitride films produced by PECVD - Applied Surface Science 252/22, , (2006) E. Minardi - Microislands and Transport in Tokamaks - J. Plasma Physics 72, , (2006) H. Henriksson, S. Conroy, G. Ericsson, G. Gorini, A. Hjalmarsson, J. Källne, M. Tardocchi, M. Weiszflog and JET-EFDA contributors - Synergetic RF and NB heating effects in JET DT plasmas studied with neutron emission spectroscopy - Nucl. Fusion 46, (2006) P. U. Lamalle, M. J. Mantsinen, J. M. Noterdaeme, B. Alper, P. Beaumont, L. Bertalot, T. Blackman, Vl. V. Bobkov, G. Bonheure, J. Brzozowski, C. Castaldo, S. Conroy, M. de Baar, E. de la Luna, P. de Vries, F. Durodi', G. Ericsson, L. G. Eriksson, C. Gowers, R. Felton, J. Heikkinen, T. Hellsten, V. Kiptily, K. Lawson, M. Laxåback, E. Lerche, P. Lomas, A. Lyssoivan, M. L. Mayoral, F. Meo, M. Mironov, I. Monakhov, I. Nunes, G. Piazza, S. Popovichev, A. Salmi, M. I. K. Santala, S. Sharapov, T. Tala, M. Tardocchi, D. Van Eester, B. Weyssow and JET EFDA contributors - Expanding the operating space of ICR on JET with a view to ITER - Nucl. Fusion 46, (2006) P. Mantica and F. Ryter - Pertubative studies of turbulent transport in fusion plasmas - C. R. Physique 7, 634 (2006) U. Tartari, G. Grosso, G. Granucci, L. V. Lubyako, A. G. Shalashov, E. V. Suvorov, F. P. Orsitto, A. Simonetto, S. Nowak, F. Volpe, A. Bruschi, F. Gandini, V. Muzzini, S. Garavaglia and G. Grossetti - Critical issues highlighted by Collective Thomson Scattering below electron cyclotron resonance in FTU - Nucl. Fusion 46, (2006) P.C. de Vries, K.M. Rantamaki, C. Giroud, E. Asp, G. Corrigan, A. Eriksson, M. de Greef, I. Jenkins, H.C.M. Knoops, P. Mantica, H. Nordman, P. Strand, T. Tala, J. Weiland, K.D. Zastrow and JET EFDA Contributors - Plasma rotation and momentum transport studies at JET - Plasma Phys. Control. Fusion 48, (2006) L. Garzotti, M. Valovic, X. Garbet, P. Mantica, V. Parail and JET EFDA contributors - Simulations of source and anomalous pinch effects on the density profile peaking of JET H-mode plasmas - Nucl. Fusion 46, (2006) F. Ryter, Y. Camenen, J. C. DeBoo, F. Imbeaux, P. Mantica, G. Regnoli, C. Sozzi, U. Stroth, ASDEX Upgrade, DIII-D, FTU, JET-EFDA contributors, TCV, Tore Supra and W&-AS Teams - Electron heat transport studies - Plasma Phys. Control. Fusion 48, 12B, B453-B463 (2006) Manini A., Angioni C., Peeters A.G., Ryter F., Jacchia A., Maggi C.F., Suttrop and the ASDEX Upgrade Team Role of T e /T i and v tor in ion heat transport of ASDEX Upgrade H-mode plasmas - Nuclear Fusion 46, (2006) M. Romanelli, M. De Benedetti, B. Esposito, G. Regnoli, F. Bombarda, C. Bourdelle, D. Frigione, C. Gormezano, E. Giovannozzi, G. T. Hoang, M. Leigheb, M. Marinucci, D. Marocco, C. Mazzotta, C. Sozzi and F. Zonca - Confinement and turbulence study in the Frascati Tokamak Upgrade high field and high density plasmas - Nucl. Fusion 46, 4, (2006) 60 IFP Activity Report

61 Conference Proceedings 2005 Nowak S., Farina D. and Ramponi G. - Astigmatic Gaussian Beams in Plasmas - Proc. 13th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, Nizhny Novgorod, Russia, May , Pg (2005) Ramponi G., Farina D. and Nowak S. - ITER ECRF Upper Launcher Optimisation Studies - Proc. 13th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, Nizhny Novgorod, Russia, May , Pg (2005) Zohm H., Farina D., Heidinger R., Lloyd B., Nowak S., Poli E., Ramponi G., Saibene G., Sauter O., Verhoeven A.G.A., Volpe F. and Westerhof E. - The ITER ECRH Upper Launcher - Physics Goals and Design Requirements - Proc. 13th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, Nizhny Novgorod, Russia, May , Pg (2005) D'Arcangelo O., Battaglia P., Bersanelli M., Figini L., Mari G., Nesti R., Pecora M., Sandri M., Simonetto A., Sozzi C., Villa F. - Performance of the Planck-LFI feed horns Qualification Model - Proc. of the 28th ESA Antenna Workshop on Space Antenna Systems and Technologies, Noordwijk, The Netherlands, 31 May - 3 June 2005, WPP-247, Part 2, pp , (2005) Yavorskij V., Kiptily V., Goloborod'ko V., Gorini G., Hawkes N., Reznik S., Schoepf K., Sharapov S., Stork D., Voitsekhovitch I. and contributors to the JET-EFDA work program - Relaxation of Fusion Alpha Distributions in Tritium NBI Experiments - Proc. 32nd EPS Conference on Plasma Phys. and Contr. Fusion Tarragona (Spain) 27thJune-1st July 2005, ECA Vol.29C, O (2005) Puiatti M.E., Valisa M., Angioni C., Carraro L., Coffey I., Garzotti L., Mantica P., Mattioli M., Sozzi C. and contributors to the EFDA-JET workprogramme Analysis of metallic impurity density profiless in low collisionality JET H-mode plasmas - 32nd EPS Conference on Plasma Physics, Tarragona (Spain), 27thJune-1st July 2005, ECA Vol.29C, O (2005) Nowak S., Granucci G., Sozzi C., Bruschi A., Esposito B., Gandini F., Panaccione L., Tudisco O., Buratti P., Cirant S., Farina D., Giovannozzi E., Mazzotta C., Ramponi G., Smeulders P., ECRH and FTU team - Electron Cyclotron Current Drive experiments in the FTU tokamak - 32nd EPS Conference on Plasma Physics, Tarragona (Spain), 27thJune-1st July 2005, ECA Vol.29C, P (2005) Granucci G., Aquilini M., Bin W., Bruschi A., Buratti P., Calabrò G., Di Giovenale S., Farina D., Gandini F., Gormezano C., Grossetti G., Mazzotta C., Mellera V., Mirizzi F., Moro A., Muzzini V., Nowak S., Panaccione L., Pericoli Ridolfini V., Petrolini P., Podda S., Sozzi C., Tuccillo A., Tudisco O., ECRH and FTU team - Quantification of suprathermal current drive on FTU - 32nd EPS Conference on Plasma Physics, Tarragona (Spain), 27thJune-1st July 2005, ECA Vol.29C, P (2005) Cenacchi G., Coppi B., Airoldi A., Bombarda F., Detragiache P., Farina D., Romanelli M. - The Scientific Program of the Ignitor Experiment - 32nd EPS Conference on Plasma Physics, Tarragona (Spain), 27thJune-1st July 2005, ECA Vol.29C, P (2005) Califano F., Galeotti L., Lontano M. - Propagation of finite amplitude disturbances in an inhomogeneous magnetized plasma - 32nd EPS Conference on Plasma Physics, Tarragona (Spain), 27thJune-1st July 2005, ECA Vol.29C, P (2005) Weber S., Lontano M., Passoni M., Riconda C., Tikhonchuk V. T. - Plasma Cavitation and Standing Solitons due to Stimulated Brillouin Pulsations - 32nd EPS Conference on Plasma Physics, Tarragona (Spain), 27thJune-1st July 2005, ECA Vol.29C, O (2005) Regnoli G., Romanelli M., Bourdelle C., De Benedetti M., Marinucci M., Pericoli V., Granucci G., Sozzi C., Tudisco O., Giovannozzi E., ECRH, LH and FTU Team - Microstability analysis of e-itbs in high density FTU plasmas - 32nd EPS Conference on Plasma Physics, Tarragona (Spain), 27thJune-1st July 2005, ECA Vol.29C, P (2005) IFP Activity Report

62 Esposito B., Granucci G., Martin-Solis J.R., Leigheb M., Gabellieri L., Gandini F., Marocco D., Mazzotta C., Smeulders P. - Mitigation of disruption-generated runaways by means of ECRH - 32nd EPS Conference on Plasma Physics, Tarragona (Spain), 27thJune-1st July 2005, ECA Vol.29C, P (2005) 2006 O. D'Arcangelo, L. Figini, A. Simonetto, S. Garavaglia, G. Mari, P. Battaglia, M. Bersanelli, M. Pecora, C. Sozzi, F. Villa - Reflection-Transmission measurements of very long millimetre-wave reciprocal components - Proc. of the 4th ESA Workshop on Millimetre Wave Technology and Application, the 8th Topical Symposium on Millimeter Waves-TSMMW2006, the 7th MINT Millimeter- Wave International Symposium, Finland February 2006, pg , (2006) P. Platania, O. D'Arcangelo, L. Figini, M. Sandri, C. Sozzi, F. Villa - Preliminary simulations of LFI Main Beam using measured Feed Horn patterns - Proc. of Science of CMB and Physics of the Early Universe, CMB2006 (051), International Conference, April 2006, Ischia, Italy G. Ericsson, E. Andersson-Sundén, H. Sjöstrand, S. Conroy, M. Gatu-Johnson, L. Giacomelli, C. Hellesen, A. Hjalmarsson, J. Källne, E. Ronchi, M. Weiszflog, G. Wikström, G. Gorini, M. Tardocchi, R. C. Pereira, A. Combo, N. Cruz, J. Sousa, C. Correia, S. Popovichev and JET EFDA contributors - Upgrade of the Magnetic Proton Recoil (MPRu) spectrometer for MeV neutrons for JET and the next step - Conference on Fast Neutron Detection and Applications (Capetown, April 2006), Proc. of Science FNDA2006(039) S. Cirant, J. Berrino, G. D Antona, E. Lazzaro, F. Gandini, P. Buratti, G. Granucci, E. Iannone, V. Mellera, V. Muzzini, P. Smeulders, O. Tudisco - Dynamic Control Of The Current Density Profile And MHD Instabilities By ECH/ECCD In Tokamaks - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 75, Santorini, Greece, May 2006 G. Granucci, S. Cirant, B. Esposito, S. Nowak, M. Aquilini, J. Berrino, W. Bin, A. Bruschi, P. Buratti, G. Calabrò, G. D Antona, S. Di Giovenale, D. Farina, L. Gabellieri, F. Gandini, G. Grossetti, E. Iannone, E. Lazzaro, M. Leigheb, D. Marocco, J. R. Martin-Solis, C. Mazzotta, V. Mellera, F. Mirizzi, A. Moro, V. Muzzini, L. Panaccione, V. Pericoli-Ridolfini, P. Petrolini, S. Podda, A. Simonetto, C. Sozzi, P. Smeulders, A. A. Tuccillo, O. Tudisco - Application of ECRH/ECCD on FTU: an Overview of Recent Results - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 101, Santorini, Greece, May 2006 C. Sozzi, A. Simonetto, S. Garavaglia and EFDA-JET Contributors - The Multichannel Extension Of The Martin-Puplett Interferometer For Perpendicular And Oblique ECE Measurements On JET - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 157, Santorini, Greece, May 2006 A. Simonetto, C. Sozzi, S. Garavaglia and EFDA-JET Contributors - Conceptual Design Of The Optical Scheme For A Multichannel Martin Puplett Interferometer For Perpendicular And Oblique ECE Measurements On JET - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 238, Santorini, Greece, May 2006 D. Farina - GRAY: a quasi-optical beam tracing code for EC absorption and current drive - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 289, Santorini, Greece, May 2006 E. Poli, D. Farina, M. A. Henderson, G. Ramponi, G. Saibene, H. Zohm - Performance studies for the ITER ECRH launchers Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 301, Santorini, Greece, May 2006 R. Prater, D. Farina, Yu. Gribov, R. W. Harvey, E. Poli, A. S. Smirnov, F. Volpe, E. Westerhof, A. Zvonkov, and ITPA Steady State Operation Topical Group - Benchmarking of ECH codes for ITER Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 312, Santorini, Greece, May IFP Activity Report

63 G. Ramponi, D. Farina, M. A. Henderson, E. Poli, G. Saibene, H. Zohm - Capabilities of the ITER ECRH/ECCD systems for extended physics application - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 351, Santorini, Greece, May 2006 W. Kasparek, M. Petelin, V. Erckmann, D. Shchegolkov, A. Bruschi, S. Cirant, M. Thumm, B. Plaum, M. Grünert, M. Malthaner, ECRH groups at IPP Greifswald, FZK Karlsruhe, and IPF Stuttgart - Fast Switching of High-Power Millimetre Waves Between Two Launchers: Concepts, Numerical Investigations and First Experiments - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 424, Santorini, Greece, May 2006 H. Shidara, M. A. Henderson, R. Chavan, D. Farina, E. Poli, G. Ramponi - ECRH Beam Optics Optimization for ITER Upper Port Launcher - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 436, Santorini, Greece, May 2006 M. A. Henderson, G. Ramponi, D. Campbell, R. Chavan, D. Farina, E. Poli, G. Saibene, K. Sakamoto, O. Sauter, A. Serikov, H. Shidara, K. Takahashi, H. Zohm, C. Zucca - Synergy Study of the Equatorial and Upper Port ITER ECH Launchers for an Enhanced Physics Performance - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 460, Santorini, Greece, May 2006 A. G. A. Verhoeven, W. A. Bongers, A. Bruschi, S. Cirant, I. Danilov, B. S. Q. Elzendoorn, Á. Fernández Curto, G. Gantenbein, M. F. Graswinckel, R. Heidinger, W. Kasparek, O. G. Kruijt, B. Lamers, B. Plaum, D. M. S. Ronden, F. C. Schüller, E. Westerhof and H. Zohm - Design of the Remote-Steering ITER ECRH Upper-Port Launcher - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 471, Santorini, Greece, May 2006 A. Moro, A. Bruschi, P. Platania, C. Sozzi - Sources Of Aberrations In The Optics For The Remote Steering ITER ECRH Upper Launcher - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 490, Santorini, Greece, May 2006 M. A. Henderson, R. Chavan, R. Bertizzolo, D. Campbell, I. Danilov, F. Dolizy, D. Farina, K. Kleefeldt, R. Heidinger, J.-D. Landis, E. Poli, G. Ramponi, G. Saibene, F. Sanchez, O. Sauter, A. Serikov, H. Shidara, P. Spaeh, H. Zohm, C. Zucca - The ITER ECH FS Launcher design for an optimized Physics Performance - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 558, Santorini, Greece, May 2006 A. Bruschi, S. Cirant, A. Moro, A. Simonetto - High-Power Millimetre-Wave Components Combining Quasi-Optics With Oversized Rectangular Corrugated Waveguide - Proc. of 14th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating, pg. 564, Santorini, Greece, May 2006 A. Mennella, B. Aja, E. Artal, M. Balasini, G. Baldan, P. Battaglia, T. Bernardino, M. Bersanelli, E. Blackhurst, L. Boschini, C. Burigana, C. Butler, B. Cappellini, F. Colombo, F. Cuttaia, O. D'Arcangelo, S. Donzelli, R. Davis, L. De La Fuente, F. Ferrari, L. Figini, S. Fogliani, C. Franceschet, E. Franceschi, T. Gaier, S. Galeotta, S. Garavaglia, A. Gregorio, M. Guerrini, R. Hoyland, N. Hughes, P. Jukkala, D. Kettle, M. Laaninen, P. M. Lapolla, D. Lawson, R. Leonardi, P. Leutenegger, G. Mari, P. Meinhold, M. Miccolis, D. Maino, M. Malaspina, N. Mandolesi, M. Maris, E. Martinez-Gonzalez, G. Morgante, L. Pagan, F. Pasian, P. Platania, M. Pecora, S. Pezzati, L. Popa, T. Poutanen, N. Roddis, M. Salmon, M. Sandri, R. Silvestri, A. Simonetto, C. Sozzi, L. Stringhetti, L. Terenzi, M. Tomasi, J. Tuovinen, L. Valenziano, J. Varis, F. Villa, A. Wilkinson, F. Winder, A. Zacchei - Calibration and testing of the Planck-LFI QM instrument - Proc. Conference on Astronomical Telescope and Instrumentation SPIE 6265, Orlando May 2006 (2006) A. G. Verhoeven, B. S. Q. Elzendoorn, W. A. Bongers, A. Bruschi, S. Cirant, I. Danilov, A. Fernandez, G. Gantenbein, M. F. Graswinckel, R. Heidinger, W. Kasparek, K. Kleefeldt, O. G. Krujit, B. Lamers, B. Piosczyk, B. Plaum, D. M. S. Ronden, G. Saibene, H. Zohm - Millimiter-wave design of the ITER ECRH launcher - International Workshop on: Strong Microwaves in Plasmas, Nyzhny Novgorod, IFP Activity Report

64 Russia, 25 July - 1 August 2006, Russian Academy of Sciences, Institute of Applied Physics, Vol. 2, 499 (2006) U. Tartari, G. Grosso, G. Granucci, L. V. Nubyako, A. G. Shalashov, E. V. Suvorov, F. P. Orsitto, A. Simonetto, S. Nowak, F. Volpe, V. Muzzini, S. Garavaglia, G. Grossetti - Evidence of Gyrotron Perturbation in Collective Thomson Scattering below Gyroresonance in FTU - International Workshop on: Strong Microwaves in Plasmas, Nyzhny Novgorod, Russia, 25 July - 1 August 2006, Russian Academy of Sciences, Institute of Applied Physics, Vol. 2, 518 (2006) E. Lazzaro, J. Berrino, S. Cirant, F. Gandini, G. Granucci - Real-Time ECE identification and ECRH/ECCD control of magnetic islands in a tokamak - International Workshop on: Strong Microwaves in Plasmas, Nyzhny Novgorod, Russia, 25 July - 1 August 2006, Russian Academy of Sciences, Institute of Applied Physics, Vol. 2, 524 (2006) S. Cirant, W. Bin, A. Bruschi, F. Gandini, G. Granucci, V. Mellera, N. Spinicchia, C. Sozzi - A family of calorimetric loads for high power millimetric wavelength beams - International Workshop on: Strong Microwaves in Plasmas, Nyzhny Novgorod, Russia, 25 July - 1 August 2006, Russian Academy of Sciences, Institute of Applied Physics, Vol. 2, 586 (2006) A. Cardinali, B. Esposito, F. Rimini, M. Brambilla, F. Crisanti, M. de Baar, E. de la Luna, P. de Vries, X. Garbet, C. Giroud, E. Joffrin, P. Mantica, M. Mantsinen, A. Salmi, C. Sozzi, D. Van Eester and JET EFDA Contributors - Modeling and analysis of the ICRH heating experiments in JET ITB regimes - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, P1.065 V. Yavorskij, V. Goloborod'ko, G. Gorini, V. Kiptily, V. Parail, K. Schoepf and JET-EFDA contributors - TF Ripple Induced Loss of NBI Ions in JET Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA, Vol. 30I, P E. Andersson Sundén, S. Conroy, G. Ericsson, M. Gatu Johnson, L. Giacomelli, C. Hellesen, A. Hjalmarsson, J. Källne, E. Ronchi, H. Sjöstrand, M. Weiszflog, G. Gorini, M. Tardocchi, A. Murari, S. Popovichev, J. Sousa, R. C. Pereira, A. Combo, N. Cruz and JET EFDA contributors Neutron emission spectroscopy diagnosis of JET D and DT plasmas with the new MPRu instrument - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol.30I, P1.071 J. Juul Rasmussen, V. Naulin, J. S. Lönnroth, P. Mantica, V. Parail and JET-EFDA Contributors - Turbulence spreading transport simulations of JET plasmas - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, P1.076 P. C. de Vries, K. M. Rantamäki, E. Asp, G. Corrigan, A. Eriksson, C. Giroud, H. C. M. Knoops, P. Mantica, H. Nordman, P. Strand, T. Tala, J. Weiland and JET EFDA Contributors - Plasma Rotation and Momentum Transport studies at JET - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, P1.083 M. Weiszflog, M. Gatu Johnson M., L. Giacomelli, A. Hjalmarsson, E. Andersson Sundén, S. Conroy, G. Ericsson, C. Hellesen, J. Källne, E. Ronchi, H. Sjöstrand, G. Gorini, M. Tardocchi, A. Murari, S. Popovichev, J. Sousa, R. C. Pereira, A. Combo, N. Cruz and JET EFDA contributors - First results from the new TOFOR neutron spectrometer at JET - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol.30I, P1.087 C. Angioni, H. Weisen, M. Maslov, A. Zabolotsky, C. Fuchs, L. Garzotti, C. Giroud, O. J. W. F. Kardaun, B. Kurzan, P. Mantica, A. G. Peeters, J. Stober, ASDEX Upgrade Team and JET EFDA contributors - Scaling of density peaking in ELMy H-mode plasmas based on a combined database of AUG and JET observations Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, P IFP Activity Report

65 P. Mantica, A. Casati, N. A. Kirneva, F. Imbeaux, A. Marinoni, T. Tala, D. Van Eester and JET EFDA contributors - Heat wave propagation in JET ITB plasmas - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, P1.091 G. Gorini, E. Andersson Sundén, L. Ballabio, S. Conroy, G. Ericsson, M. Gatu Johnson, L. Giacomelli, C. Hellesen, A. Hjalmarsson, J. Källne, A. Murari, H. Sjöstrand, E. Ronchi, M. Tardocchi, M. Weiszflog and JET EFDA contributors - High-energy fuel ion diagnostics on ITER derived from neutron emission spectroscopy measurements on JET DT plasmas - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol.30I, P1.109 A. Airoldi, F. Bombarda, G. Cenacchi, B. Coppi and D. Farina - The groundwork for the Ignitor experiment - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, P1.196 B. Coppi, D. A. D'Ippolito, S. I. Krasheninnikov, M. Lontano, J. R. Myra, P. Nataf, D. A. Russel - Incentives for and developments of the accretion theory of spontaneous rotation - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, O4.07 S. Ratynskaia, M. De Angeli, U. de Angelis, C. Marmolino, G. Capobianco, M. Lontano, E. Lazzaro, G. Morfill - Effect of dust on plasma fluctuation spectra - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, P4.041 M. C. Varischetti, B. Coppi, E. Lazzaro, M. Lontano - Slab ITG modes in the presence of a sheared ion velocity - Proc. 33rd EPS Conference on Plasma Phys. and Contr. Fusion, Rome, Italy, June 2006, ECA Vol. 30I, P5.079 G. Saibene, R. Heidinger, M. Henderson, A. G. A. Verhoeven, H. Zohm, G. Ramponi, A. Bruschi, D. Campbell, R. Chavan, S. Cirant, I. Danilov, B. Elzendoorn, D. Farina, W. Kasparek, K. Kleefeld, E. Poli, D. Ronden, O. Sauter, A. Serikov, P. Spaeh - Design of the ITER Electron Cyclotron Wave Launcher for NTM Control - Proc. 21st IAEA Fusion Energy Conference, Chengdu (China), October M. A. Henderson, R. Chavan, R. Bertizzolo, A. Bruschi, D. Campbell, E. Ciattaglia, S. Cirant, I. Danilov, F. Dolizy, D. Farina, R. Heidinger, K. Kleefeldt, J.-D. Landis, A. Moro, E. Poli, G. Ramponi, G. Saibene, O. Sauter, A Serikov, H. Shidara, P. Spaeh, V. Udintsev, H. Zohm, C. Zucca - The ITER ECH FS Upper Launcher mm-wave Design based on a Synergy Study with the Equatorial Launcher - Proc. 21st IAEA Fusion Energy Conference, Chengdu (China), October O. Sauter, M. A. Henderson, G. Ramponi, H. Zohm, C. Zucca - Partial Stabilization and Control of Neoclassical Tearing Modes in Burning Plasmas - Proc. 21st IAEA Fusion Energy Conference, Chengdu (China), October J. R. Myra, J. Boedo, B. Coppi, D. A. D'Ippolito, S. I. Krasheninnikov, B. P. LeBlanc, M. Lontano, R. Maqueda, D. A. Russel, D. P. Stotler, M. C. Varischetti, S.J. Zweben and the NSTX Team - Blob transport models, experiments, and the accretion theory of spontaneous rotation - Proc. 21st IAEA Fusion Energy Conference, Chengdu (China), October C. Giroud, C. Angioni, G. Bonheure, I. Coffey, N. Dubuit, X. Garbet, R. Guirlet, P. Mantica, V. Naulin, M. E. Puiatti, M. Valisa, A. D. Whiteford, K-D. Zastrow, M. N. A. Beurskens, M. Brix, E. de la Luna, K. Lawson, L. Lauro-Taroni, A. Meigs, M. O'Mullane, T. Parisot, C. Perez Von Thun, O. Zimmermann and the JET-EFDA Contributors - Progress in understanding of impurity transport at JET - Proc. 21st IAEA Fusion Energy Conference, Chengdu (China), October H. Weisen, C. Angioni, M. Maslov, A. Zabolotsky, M. Beurskens, C. Fuchs, L. Garzotti, C. Giroud, P. Mantica, D. Mazon, L. Porte, J. Stober, JET-EFDA contributors, the ASDEX Upgrade Team and the IFP Activity Report

66 TCV Team - Peaked Density Profiles in Low Collisionality H-modes in JET - Proc. 21st IAEA Fusion Energy Conference, Chengdu (China), October T. Tala, Y. Andrew, K. Crombé, P.C. de Vries, X. Garbet, N. Hawkes, H. Nordman, K. Rantamäki, P. Strand, A. Thyagaraja, J. Weiland, E. Asp, Y. Baranov, C. Challis, G. Corrigan, A. Eriksson, C. Giroud, M. D. Hua, I. Jenkins, H.C.M. Knoops, X. Litaudon, P. Mantica, V. Naulin, V. Parail, K.D. Zastrow and JET-EFDA contributors - Overview of Toroidal and Poloidal Momentum Transport Studies in JET - Proc. 21st IAEA Fusion Energy Conference, Chengdu (China), October B. Coppi, A. Airoldi, R. Albanese, F. Alladio, A. Bianchi, F. Boert, F. Bombarda, A. Cardinali, B. Carmignani, G. Cenacchi, A. Ciampichetti, A. Coletti, R. Coletti, C. Crescenzi, A. Cucchiaro, P. Detragiache, D. Farina, M. Fersini, A. Frattolillo, P. Frosi, A. Licciulli, F. Lucca, F. Lucchini, G. Maddaluno, R. Maggiora, A. Marin, G. Mazzone, S. Migliori, B. Parodi, S. Pierattini, G. Pizzicaroli, A. Pizzuto, G. Ramogida, M. Roccella, M. Romanelli, G. Rubinacci, M. Santinelli, M. Sassi, F. Subba, G. Toselli, F. Villone, R. Zanino, M. Zucchetti, H. G. Wobker Highlights of the Physics and Technology for the Ignitor Experiment - Proc. 21st IAEA Fusion Energy Conference, Chengdu (China), October D. Farina - Quasi-optical Propagation of a EC Gaussian Beam, Absorption and Current Drive in Tokamaks - Proc. Joint Varenna-Lausanne International Workshop on Theory of Fusion Plasmas, Varenna, Italy, Aug Sept. 1, 2006, AIP Conf. Proc. 871, 77 (2006) M. Lontano, M. C. Varischetti, E. Lazzaro - Effects of a sheared ion velocity on the linear stability of ITG modes - Proc. Joint Varenna-Lausanne International Workshop on Theory of Fusion Plasmas, Varenna, Italy, Aug Sept. 1, 2006, AIP Conf. Proc. 871, 374 (2006). Conference Presentations 2005 Lontano M., Passoni M., Riconda C., Tikhonchuk V. T., Weber S. - Electromagnetic Solitons in the Saturation Regime of the Stimulated Brillouin Backscattering - Second International Conference on the Frontiers of Plasma Physics and Technology, Goa, India, February 2005 Califano F., Lontano M. - Propagation of Large Amplitude Electrostatic Disturbances in a Inhomogeneous Vlasov Plasma - Second International Conference on the Frontiers of Plasma Physics and Technology, Goa, India, February 2005 Spinicchia N., Angella G., De Angeli M., Gervasini G., Signorelli E. - Growth of thin films and hydrogen production in a cusp plasma device - E-MRS Spring Meeting, Strasbourg, France, Presentation PS-K/PI.50, May 31 - June 3, 2005 L. Laguardia, D. Ricci, E. Vassallo, A. Cremona, E. Mesto, F. Ghezzi, F. Dell'Era - Deposition of super-hydrophobic and oleophobic fluorocarbon films in RF glow discharges - Times of polymer & composites conference, June 18-22, 2006, Ischia (Italy) M. Lontano, M. Passoni - Laser-based ion acceleration: theory and experiments - 43rd Conference on "Matter in super-intense laser fields", June 27 - July 5, 2006, Erice (Tp) Henderson M. A., Hogge J.-P., Chavan R., Heidinger R., Nikkola P., Ramponi G., Saibene G., Sanchez F., Sauter O., Serikov A., Shidara H., Zohm H. - The Front Steering Launcher Design for the ITER ECRH Upper Port - US/JPN/EU RF Tech. Ex. Workshop, California, USA, July 2005 Gervasini G., De Angeli M., Amedeo P., Angella G., Gatto G., Schiavone R., Signorelli E., Spinicchia N. - Hydrogen formation by methane cracking in a cusp plasma device - 17th International Symposium on Plasma Chemistry, Toronto (Canada), 7th - 12th August IFP Activity Report

67 Passoni M., Lontano M., Riconda C., Tikhonchuk V. T., Weber S. - Electromagnetic Droplets created by Stimulated Brillouin Backscattering - Fourth International Conference on Inertial Fusion Science and Applications, Biarritz, France, 4-9 September 2005 Lontano M., Passoni M., Riconda C., Tikhonchuk V. T., Weber S., Ghizzo S. - Electromagnetic Solitary Waves created by Stimulated Brillouin Backscattering - Final INTAS Meeting, Belfast, U.K, 5-7 September 2005 Lontano M., Passoni M. - Hot Electron Distribution at the Sharp Interface between High Density Matter and Vacuum - Final INTAS Meeting, Belfast, U.K, 5-7 September 2005 Laguardia L., Vassallo E., Cremona A., Cappitelli F., Zanardini E., Vicini S., Princi E., Mesto E., Cagna M. - Conservation of biodeteriorated ancient documents and paper consolidation by plasma treatments - 14th Triennial Meeting ICOM, Hague, Netherlands, September 12-16, 2005 Henderson M, Chavan R., Heidinger R., Ramponi G., Saibene G., Sanchez F., Sauter O., Shidara H., and Zohm H. - The Design and Physics Perormance of the ITER Upper Port ECH Front Steering Launcher - 26th IEE/NPSS Symposium on Fusion Engineering, September , Knoxville (USA) Laguardia L., Ricci D., Vassallo E., Cremona A. - Deposition of perfluorinated polymer coating in RF glow discharge - European Conference on Applications of Surface and Interface Analysis, ECASIA, Vienna, Austria, September 25-30, 2005 Lontano M., Passoni M., Riconda C., Tikhonchuk V. T., Weber S. - Electromagnetic Solitons produced by Stimulated Brillouin Pulsations in Plasmas XCI Congresso Nazionale della Societa Italiana di Fisica, Catania Settembre 2005 Farina D. - A quasi-optical ray tracing code for EC absorption and current drive - 47th Annual Meeting of the Division of Plasma Physics, paper QP1 46 Denver, Colorado, USA October 24-28, 2005, Bulletin of the American Physical Society, 50, 276 Airoldi A., Farina D., Coppi B., Bombarda F., Cenacchi G., Detragiache P., Romanelli M. - The Ignitor Experiment: Deuterium-Tritium Phase - 47th Annual Meeting of the Division of Plasma Physics, paper KP1 43 Denver, Colorado, USA October 24-28, 2005, Bulletin of the American Physical Society, 50, 198 (2005) Lazzaro E., Berrino J., Cirant S., D'Antona G., Gandini F., Granucci G., Iannone F. - Automatic realtime tracking and stabilization of magnetic islands in a Tokamak by ECCD/ECRH - Workshop on Active Control of MHD Stability University of Wisconsin, Madison (USA) October 31 - November 2, D. Farina - GRAY: a quasi-optical beam tracing code for Electron Cyclotron absorption and current drive - IMP-5 Project meeting, EFDA's Task Force "Integrated Tokamak Modelling", 10-11th January 2006, Cadarache (France) Cenacchi G., Airoldi A., Farina D., and Coppi B. - Physics with reduced parameters by the Ignitor experiment - April Meeting 2006 of the Division of Plasma Physics, K , Dallas, Texas, April 22-25, 2006, Bulletin of the American Physical Society, 51, No.2, pg 127 G. Gervasini, M. De Angeli, P. Amedeo, R. Schiavone - A Steady State Cusp Device for Plasma Studies and Technological Applications - 6th International Conference on Open Magnetic Systems for Plasma Confinement, July 2006, Tsukuba, Japan P. Mantica, X. Garbet, V. Naulin, M. Nora, J. Juul Rasmussen, T. Tala, A. Thyagaraja and JET EFDA Contributors - Fast core response to edge cooling in JET: experiments and modeling - 11th EU- US Transport Task Force Workshop, Marseille (France) September 4-7, 2006 IFP Activity Report

68 E. Vassallo, M. Catellani, F. Dell'Era, F. Ghezzi, L. Laguardia, S. Luzzati, D. Ricci - Conductive polymer films produced by plasma polymerization - Tenth International Conference on Plasma Surface Engineering, Garmisch-Partenkirchen (Germany) September 10-15, 2006 M. A. Henderson, S. Alberti, P. Benin, T. Bonicelli, R. Chavan, D. Campbell, S. Cirant, G. Dammertz, O. Dormicchi, O. Dumbrajs, D. Fasel, T. P. Goodman, R. Heidinger, J. P. Hogge, W. Kasparek, C. Lievin, B. Piosczyk, E. Poli, G. Ramponi, G. Saibene, O. Sauter, A. Serikov, G. Taddia, M. Thumm, M. Q. Tran, A. G. A. Verhoeven, H. Zohm - EU Developments of the ITER ECRH System - 24th Symposium on Fusion Technology, September 2006, Warsaw, Poland, Presentation PL2-O- 554 S. Garavaglia, A. Simonetto, C. Sozzi - Mechanical realization of a multichannel Martin Puplett interferometer for perpendicular and oblique ECE measurements on JET - 24th Symposium on Fusion Technology, September 2006, Warsaw, Poland, Presentation P1-D-212 W. Bin, A. Bruschi, S. Cirant, V. Erckmann, F. Gandini, G. Granucci, F. Hollmann, H.P. Laqua, V. Mellera, V. Muzzini, A. Nardone, F. Noke, B. Piosczyk, F. Purps, T. Rzesnicki, M. Schmid, C. Sozzi, W. Spies, N. Spinicchia, M. Stoner - Advances in highpower calorimetric matched loads for short pulses and CW gyrotrons - 24th Symposium on Fusion Technology, September 2006, Warsaw, Poland, Presentation P3-B-3I6 A. G. A. Verhoeven, W. A. Bongers, A. Bruschi, I. Danilov, B. S. Q. Elzendoorn, À. Fernández, G. Gantenbein1, M. F. Graswinckel, M. Henderson, R. Heidinger, W. Kasparek, O. G. Kruijt, B. Lamers, B. Plaum, D. M. S.Ronden, G. Saibene, F. C. Schüller, E. Westerhof and H. Zohm - Design And Test Of The Remote-Steering Iter Ecrh Upper-Port Launcher - 24th Symposium on Fusion Technology, September 2006, Warsaw, Poland, Presentation P3-B-2O7 E. Vassallo, L. Laguardia, G. Bonizzoni, F. Cappitelli, A. Cremona, E. Mesto, S. Vicini - Decontamination and consolidation of biodeteriorated ancient paper by plasma processing - 3rd International Workshop on: Science, Technology and Cultural Heritage, Cassino, Italy, 4-6 ottobre 2006 M. Petelin, A. Bruschi, V. Erckmann, W. Kasparek - FADIS: Project for Fast Directional Switching of Discrete High Power - Joint 23th Int. Conf. on Infrared and Millimeter Waves and 12th Int. Conf. on Terahertz Electronics, Joint 31st International Conference on Infrared and Millimeter Waves and 14th International Conference on Terahertz Electronics, September 18th to 22nd 2006, Shanghai, China. A. Airoldi, B. Coppi, F. Bombarda, G. Cenacchi, P. Detragiache Validity of the objectives and solutions of the Ignitor program - 48th Annual Meeting of the Division of Plasma Physics, paper NP1-2, Philadelphia, Pennsylvania, USA, Oct Nov , Bulletin of the American Physical Society, 51, 190 (2006) A. Cardinali, G. Cenacchi, A. Airoldi, B. Coppi ICRH physics and Ignitor experiments with reduced parameters - 48th Annual Meeting of the Division of Plasma Physics, paper NP1-5, Philadelphia, Pennsylvania, USA, Oct Nov , Bulletin of the American Physical Society, 51, 191 (2006) C. Sozzi, S. Garavaglia, G. Grossetti, S. Nowak, A. Simonetto, E. De La Luna, J. Fessey, M. Zerbini and JET-EFDA collaborators - First operation of the multi-channel Fourier Transform spectrometer for perpendicular and oblique ECE measurements at JET - 48th Annual Meeting of the Division of Plasma Physics, paper NP1-37, Philadelphia, Pennsylvania, USA, Oct Nov , Bulletin of the American Physical Society, 51, 197 (2006) M. Lontano, M. C. Varischetti, E. Lazzaro - On the effects of a non-uniform longitudinal ion flow on the linear ITG mode stability - 48th Annual Meeting of the Division of Plasma Physics, paper UP1-68, Philadelphia, Pennsylvania, USA, Oct Nov , Bulletin of the American Physical Society, 51, 279 (2006) 68 IFP Activity Report

69 Scientific and technical reports 2005 Farina D. - GRAY: a quasi-optical ray tracing code for electron cyclotron absorption and current drive in tokamaks FP 05/01 May 2005 The 3rd International Conference on Superstrong Fields in Plasmas- Programme and Abstracts FP 05/02 September 2005 Farina D. - The relativistic dispersion relation for electron cyclotron waves FP 05/03 September 2005 Ramponi G., Farina D., Nowak S. - Physics Analysis of the ITER ECRH & ECCD Upper Launcher Design for NTM Stabilisation-Final Report on EFDA Task TW3-TW4-TPHE-ECHULA FP 05/04 January 2005 Gervasini G., De Angeli M., Gittini G. - Design and Test of Magnetic Shields for Quadrupole Mass Spectrometers FP 05/05 October 2005 De Angeli M., Gervasini G., Gittini G. - Design and Test of Magnetic Shields for Turbomolecular Pumps FP 05/06 December 2005 Cenacchi G. e Airoldi A. - JETTO per Ignitor FP 05/07 December 2005 Ghezzi F. - Surface analysis of Tokamak tiles FP 05/08 December 2005 Bruschi A., Cirant S., Nowak S. - Conceptual design of the end mirror set FINAL REPORT for Deliverable (a) 2.1 EFDA Task TW3-TPHE-ECHULB4 "Upper Launcher for ITER ECH&CD System" FP 05/09 December 2005 Cirant S., Bruschi A. - Beam dump & calorimetric measurements in a transmission line mock-up at 140 Ghz FP 05/10 December 2005 Bruschi A., Cirant S. - Detailed design of end-mirror, including material selection & Cooling arrangements FINAL REPORT for Deliverable (a) 2.1 EFDA Task TW3-TPHE-ECHULB4 "Upper Launcher for ITER ECH&CD System" FP 05/11 December 2005 Bruschi A., Cirant S., Moro A. - Detailed design of (fixed) end mirror for high power/cw operations FP 05/12 December G. Ramponi, D. Farina, S. Nowak - Physics Analysis of the ITER ECRH & ECCD Upper Launcher Design for NTM Stabilisation-Final Report on deliverables for EFDA Task TW5-TPHE-ECHULA FP 06/01 February 2006 E. Minardi, C.Sozzi - Stationary Magnetic Entropy Tokamak States and Experimental Observations FP 06/02 June 2006 IFP Activity Report

70 F. Ghezzi, Bojan Zajec, G. Gatto - MICROJET PLASMA DISCHARGES: an experimental investigation in view of a PLASMA-WALL DIAGNOSTIC application FP 06/03 December 2006 Moro A., Bruschi A. - Computation of first-order beam characteristics of the dogleg option for the RS design FINAL REPORT for Deliverable (a).2.1 EFDA Task TW5-TPHE-ECHULB1 "Upper Launcher for ITER ECH&CD System" FP 06/04 June 2006 Moro A., Bruschi A. - Inclusion in the optimisation of double curvature effects and general astigmatism. Deformation calculations based on the cooling layout for the dogleg option for the RS design FINAL REPORT for Deliverable (a) 7.1 EFDA Task TW5-TPHE-ECHULB1 "Upper Launcher for ITER ECH&CD System" FP 06/05 June 2006 A. Airoldi, G. Cenacchi, D. Farina, S. Nowak - JETTO per ITER FP 06/06 Dicembre 2006 P. Platania, C. Sozzi - Pattern calculations for Dogleg configuration FINAL REPORT for Deliverable (a).3.1 EFDA Task TW5-TPHE-ECHULB1 "Upper Launcher for ITER ECH&CD System" FP 06/07 December 2006 S. Garavaglia, A. Simonetto, C. Sozzi and EFDA-JET Contributors - Mechanical realization of a multichannel Martin Puplett interferometer for perpendicular and oblique ECE measurements on JET FP 06/08 December 2006 U. Tartari, G. Grosso, G. Granucci, F. Gandini, S. Garavaglia, G. Grossetti, A. Simonetto, V. Mellera, V. Muzzini, L. V. Lubyako, A. G. Shalashov, F. P. Orsitto, G. Ciccone and F. Volpe - Evolution of the mm-wave Collective Thomson Scattering system of the high-field tokamak FTU FP 06/09 December 2006 M. A. Henderson, R. Chavan, D. Farina, R. Heidinger, G. Ramponi, G. Saibene - Interface Issues related to the ITER ECH system CRPP Report LRP 828/06, December 2006 crppwww.epfl.ch/pubarchive/2006/lrp2006/lrp_828_06.pdf Books Superstrong fields in plasmas 3 rd International Conference on Superstrong Fields in Plasmas, Varenna, Italy 2005 Editors: D. Batani and M. Lontano AIP Conference Proceedings 827, AIP M. Lontano and M. Passoni Ultraintense Radiation in Plasmas (Part I) in Progress in Ultrafast Intense Laser Science I Editors: Yamanouchi, K.; Chin, S.L.; Agostini, P.; Ferrante, G. Vol 84 of the Springer Series In Chemical Physics, 2006 ISBN: IFP Activity Report

71 10. Acronym List AUG Asdex Upgrade CMB Cosmic Microwave Background CNRS Centre Nationale de la Recherche Scientifique - France CTS Collective Thomson Scattering CRE Centro Ricerca Energia CRPP Centre de Recherches en Physique des Plasmas - Lausanne DBD Dielectric Barrier Discharge DSC Differential Scanning Calorimeter EC Electron Cyclotron ECCD Electron Cyclotron Current Drive ECE Electron Cyclotron Emission ECRH Electron Cyclotron Resonance Heating ECWGB Electron Cyclotron Wave Gaussian Beam EC14 14 th Electron Cyclotron Workshop EFTS European Fusion Training Scheme EH Electron Hole ELM Edge Localized Mode EM ElectroMagnetic EPL Extended Physics Launcher ERCAR ERosion CARbon ESEM Enviromental Scanning Electron Microscopy FTU Frascati Tokamak Upgrade GRAY Gaussian RAY HFI High Frequency Instrument JET Joint European Tokamak IAP Institute Applied Physics IH Ion Hole ICRH Ion Cyclotron Resonance Heating IENI Istituto per l Energetica e le interfasi IFP Istituto di Fisica del Plasma ITB Internal Transport Barrier ITG Ion Temperature Gradient ITER International Thermonuclear Experimental Reactor ITPA-SSO International Tokamak Physics Activity Steady State Operation LBO Laser Blow Off LHCD Lower Hybrid Current Drive LFI Low Frequency Instrument LIDAR Laser Imaging Detection and Ranging LP Langmuir Probe LTE Langmuir Probe MHD MagnetoHydroDynamic MPR Magnetic Proton Recoil MWA MicroWave Access NBI Neutral Beam Injection IFP Activity Report

72 NTM OES OLED OMT PCM RES RF SBBS SOL SPECE TFT TOFOR Neoclassical Tearing Mode Optical Emission Spectroscopy Organic Light Emitting Diode OrthoMode Transducer Polymeric Composite Material Relativistic Electromagnetic Soliton Radio Frequency Stimulated Brillouin Back-Scattering Scrape Off Layer Spectrum ECE Task Force Transport Time Of Flight Optimized Rate 72 IFP Activity Report