'Toroidal rotation' diaporamas de présentation

21 st IAEA Fusion Energy Conference Summary Innovative Concepts Confinement & performance

21 st IAEA Fusion Energy Conference Summary Innovative Concepts Confinement & performance. Jerome PAMELA, EFDA With the kind support of A.Becoulet (CEA), D.Borba (EFDA) and R.Kamendje (EFDA).

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Primary experimental results of suppressing MHD instabilities in HT-7 by biased electrode

HT-7 Data Meeting and Workshop, July 19-20. Primary experimental results of suppressing MHD instabilities in HT-7 by biased electrode. Zhong Fangchuan, Luo Jiarong Shu Shuangbao College of Science, Donghua University Shanghai, 201620. Outline. Introduction Experimental Setup Results

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T. Nakano J apan A tomic E nergy A gency

3Sep2013 ADAS Workshop Badhonnef, GE. W transport studies in JT-60U. T. Nakano J apan A tomic E nergy A gency. Tungsten: a candidate for PFCs in reactors. Tungsten: suitable for plasma facing components for reactors High melting point Low fuel retention

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Kinetic effects on the ideal-wall limit and the resistive wall mode

NSTX-U. Supported by . Kinetic effects on the ideal-wall limit and the resistive wall mode . Coll of Wm & Mary Columbia U CompX General Atomics FIU INL Johns Hopkins U LANL LLNL Lodestar MIT Lehigh U Nova Photonics Old Dominion ORNL PPPL Princeton U Purdue U SNL

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Spontaneous stationary toroidal rotation in the TCV tokamak

Spontaneous stationary toroidal rotation in the TCV tokamak. A. Scarabosio, A. Bortolon, B. P. Duval, A. Karpushov and A. Pochelon 10 th ITPA TP Group Meeting. Layout of the talk. The DNBI and CXRS diagnostic on TCV - The effect of the DNBI on toroidal rotation.

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Predictive Modelling of Plasma Rotation (examples from ITPA ITB database)

Predictive Modelling of Plasma Rotation (examples from ITPA ITB database). V.V. Parail 1 T. Tala 2 , A. Becoulet 3 , G. Corrigan 1 ,X. Garbet 3 , D. Heading 1 , X. Litaudon 3 , P.I. Strand 4 and J. Weiland 4

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K.Ida, M.Yoshinuma, LHD experimental group National Institute for Fusion Science 1 April 2009

Non-diffusive terms of momentum transport as a driving force for spontaneous rotation in toroidal plasmas. K.Ida, M.Yoshinuma, LHD experimental group National Institute for Fusion Science 1 April 2009 Transport & Confinement ITPA Meeting JAEA, Naka Japan. OUTLINE. Introduction

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PTRANSP Simulations of Toroidal Momentum Transport using GLF23 and Weiland Models

PTRANSP Simulations of Toroidal Momentum Transport using GLF23 and Weiland Models. A. Kritz, F. D. Halpern, C. Wolfe, G. Bateman, A. Pankin Department of Physics, Lehigh University, Bethlehem, PA R. Budny, D. McCune Princeton Plasma Physics Laboratory, Princeton, NJ ITPA May 2007.

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Rotation inversion vs density and current, in limited and diverted L-mode plasmas on C-MOD

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Japan Atomic Energy Agency

Japan Atomic Energy Agency Naka Fusion Institute. Dependence of H-mode pedestal and heat transport on toroidal rotation in JT-60U. H. Urano, H. Takenaga, T. Fujita, Y. Kamada, K. Kamiya, Y. Koide, N. Oyama, M. Yoshida and the JT-60 Team. Japan Atomic Energy Agency.

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Transport Studies in NCSX D. R. Mikkelsen For the NCSX Research Team NCSX Research Forum

Transport Studies in NCSX D. R. Mikkelsen For the NCSX Research Team NCSX Research Forum PPPL, December 7, 2006. Overview. Goals Transport experiments in FY11 Diagnostics needed Upgrades to enhance transport studies Transport analysis tools Summary. FY11 Transport-related Goals.

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JET discharges (C wall) selected for GLF23 validation

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