PPT-Modeling of plasma stability in advanced divertor configura

D A Baver J R Myra Lodestar Research Corporation M V Umansky Lawrence Livermore National Laboratory Lodestar Modeling of plasma stability in advanced divertor configurations with ArbiTER. B. H. Mills, and J. D. Rader. G. W. Woodruff School of Mechanical Engineering. Updated Thermal Performance of Finger-Type Divertors. ARIES Meeting (6/12). 2. Objectives / Motivation. Objectives. Evaluate thermal performance of gas-cooled . Teresa Fuller. GSK. Stability Indicating Assays for Dose Formulation Stability Testing. Stability Studies for Dose Formulations. What the white paper says. What is a stability indicating assay?. So do we need a stability-indicating assay?. Vacuum ultraviolet and Ultraviolet Spectrometers for Real-time . Radiative. . Divertor. Feedback Control in the NSTX-U . Tokamak.  . Madison, WI, 5-9 June 2016, 2016 . To prevent excessive erosion and thermal damage of . Hunter Kenyon, Giovanni Maronati, Kumar Singh. Introduction. For a reactor to operate in steady state:. Fresh fuel must be added at the rate at which it is consumed. Fuel must be heated, ideally by the reactions themselves. Jake Blanchard. University of Wisconsin – Madison. August 2012. Introduction. The ARIES Project is exploring the feasibility of using tungsten as a structural material for plasma-facing components.  . . Y. Takeiri. . for LHD Experiment Group. National Institute for Fusion Science, . National Institutes of Natural Sciences, Japan. SOKENDAI, Japan. Fusion Power Associates, 37th Annual Meeting and Symposium. 1. , M.L. Reinke. 2. , V. . . Soukhanovskii. 3. , A. Brooks. 1. , . R. Kaita. 1. , . R. Maingi. 1. , . J. Menard. 1. , M. Ono. 1. , C. . Skinner. 1. , . K. Tresemer. 1. , . and the NSTX-U Team. 1. Princeton Plasma Physics Laboratory. Maxwellian. effects and intense . divertor. stray light. A. .. B. . . Kukushkin. 1,2. , . V. .. S. . . Neverov. 1. , . A. .. G. . . Alekseev. 1. , . S. .. W. . . Lisgo. 3. , . A. .. S. . . Kukushkin. Introducing Anisotropic . Ion . Temperatures and Virtual . Divertor. Model. 非等方イオン. 温度と仮想ダイバータモデルを導入した. SOL-. ダイバータプラズマシミュレーション. Overview of NSTX-U Research Program Progress and Plans. NSTX-U PAC 37. PPPL B318. January 26-28, . 2016. Events s. ince . PAC-35. Charge Questions. Mission and Capabilities of NSTX-U. Research Goals and Milestones. . 24. th. IAEA Fusion Energy Conference,. San Diego, Oct. 2012. Y. . Kamada. , . P. . Barabaschi. , S. . . Ishida,. The . JT-. 60SA Team,. JT-60SA Research Plan Contributors. . (392 persons, . 15 JA institutes, 23 EU Institutes). . 24. th. IAEA Fusion Energy Conference,. San Diego, Oct. 2012. Y. . Kamada. , . P. . Barabaschi. , S. . . Ishida,. The . JT-. 60SA Team,. JT-60SA Research Plan Contributors. . (392 persons, . 15 JA institutes, 23 EU Institutes). Bhat. , . Gandhinagar. ADITYA . Upgradation. with . Divertor. Configuration. Contributions from:. Deepti. Sharma . –. Equilibrium study (IPREQ). Richa. . Bandyopadhyay. . –. Transport simulation (TSC). of plasma . parameters. and confinement, discussion . with. WP2. Injection technique, . comparison. of simulation . with. . experiments. . Definition. of laser . parameters. and . their. . stability.