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. Seung. Bo . Shim. a. , Jin-Woo . Park. b. , . Hyunsun. . Han. c. , . Hae. June . Lee. a. , Yong-Su Na. b. , Jin Yong . Kim. c. a. Pusan. National University, . Busan. , Korea. b. Seoul. National University, Seoul, Korea. V. A. Soukhanovskii . Lawrence Livermore National Laboratory. JI2.00002. 52nd Annual Meeting of the APS DPP. Chicago, IL. Tuesday, November 9, 2010. NSTX. Supported by . College W&M. Colorado Sch Mines. 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.  . . 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. eV. range where GROSS sputtering yield of tungsten drops to ~ 10 X greater than the required NET sputtering yield.. Reactor . divertor. lifetime ~10. 8. s requires net erosion rate of 10. -6. . ~ 100 X required net yield. 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. . 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). divertor. code and analysis of detached . divertor. plasmas. a. Satoshi. Togo. , . b. Makoto. Nakamura, . c. Katsuhiro. Shimizu,. d. Tomonori. Takizuka, . b. Kazuo. Hoshino, . a. Yuichi. Ogawa. Innovative Physics and Technology Solutions for *Work supported by US DoE awardsS.J. Wukitch TOFE 2014 High Field Path to Magnetic Fusion EnergyToobtainfusionenergy,plasmapressureisbalancedbymagnetic 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.