Heat flux deposition pattern on the inner first wall of Tore Supra

International audienceThe Inner First Wall (IFW) is the main limiter in Tore Supra for long and powerful discharges. The original graphite IFW was partly damaged by 8 years of operation and a sector of 60° was replaced between 1995 and 1997 by CFC brazed elements. They are designed to accept twice as much flux (2 MW/m²) as the older ones and are expected to be more resilient. The new elements gave the opportunity to install diagnostics (thermocouples and langmuir probes) on a poloidal sector, to characterise the behaviour of the new IFW and especially the heat flux profile. The pattern doesn't follow the cosine law and is governed by strong perpendicular heat flux and abnormal deposition at the contact point between the limiter and the plasma. The most energetic shots of the last campaign showed that the IFW could be loaded with twice the power deposited during these shots

Interaction pastille-gaine. Modele mecanique et chimique

Available from CEN Saclay, Service de Documentation, 91191 Gif-sur-Yvette Cedex (France) / INIST-CNRS - Institut de l'Information Scientifique et TechniqueSIGLEFRFranc

Calibration procedures of the Tore-Supra infrared endoscopes

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Elements pour un guide de conception thermique et energetique des verandas

Available from INIST (FR), Document Supply Service, under shelf-number : RP 400 (2051) / INIST-CNRS - Institut de l'Information Scientifique et TechniqueSIGLEAgence de l'Environnement et de la Maitrise de l'Energie (ADEME), 75 - Paris (France)FRFranc

Heat flux decay length during RF power operation in the Tore Supra tokamak

International audienceThe upgrade of its ion cyclotron resonance (ICRH) and lower hybrid current drive (LHCD) heating systems makes the Tore Supra (TS) tokamak particularly well suited to address the physics and technology of high-power and steady-state plasma-surface interactions. High radio frequency (RF) heating powers have been successfully applied up to 12.2 MW coupled to the plasma, in which about 7.85 MW flows through the scrape-off layer. Thermal calculation based on thermography measurements gives the heat flux density distribution on the TS toroidal limiter located at the bottom of the machine. The target heat flux densities are divided by the incidence angle of the field lines with the surface and mapped to the magnetic flux surface to evaluate the power flowing in the scrape-off layer (SOL). The power profile shows a narrow component near the last closed flux surface and a wide component in the rest of the SOL. The narrow component is attributed to significant cross-field heat flux density around the plasma contact point, about 0.8% of the parallel heat flux density in the SOL, when incident angles are nearly tangential to the surface. The wide component is used to derive the experimental heat flux decay length (lambda(q)) and parallel heat flux in the SOL. The power widths are measured for a series of 1 MA/3.8 T discharges involving a scan of RF injected power 3.5 <= P-tot <= 12.2 MW. Independently of the heating power, we measured lambda(q,OMP) = 14.5 +/- 1.5 mm at the outer mid-plane and parallel heat flux in the SOL in the range 130 <= Q(parallel to)(LCFS) <= 490 MW m(-2). TS values obtained with L-mode limiter plasmas are broader than those derived from L-mode divertor plasmas, confirming earlier results obtained with an ohmically heated plasma leaning on the inboard wall of TS

Note d'avancement 'programme habitat tertiaire', mai 1990 - avril 1991

Available at INIST (FR), Document Supply Service, under shelf-number : RP 400 (1643) / INIST-CNRS - Institut de l'Information Scientifique et TechniqueSIGLEFRFranc

Study of heat flux deposition on the limiter of the Tore Supra tokamak

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Rapport d'avancement semestriel GENEC 1991. Mai 1991 - Decembre 1991 Note technique DTE/SCC/LVT/92-012

SIGLEAvailable at INIST (FR), Document Supply Service, under shelf-number : RP 400 (1682) / INIST-CNRS - Institut de l'Information Scientifique et TechniqueFRFranc