PPT-Divertor plasma temperature in the ~ 10

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. 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. the Czech Republic. Radomir Panek. Institute of Plasma Physics, ASCR, Czech Republic. R. Panek. 1. Participation of Czech Institutions. Coordinated by Institute . of Plasma Physics AS CR. Institutes involved:.  . . 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. Radomir Panek. Institute of Plasma Physics, ASCR, Czech Republic. R. Panek. 1. Participation of Czech Institutions. Coordinated by Institute . of Plasma Physics AS CR. Institutes involved:. Institute of Plasma Physics AS CR. 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. Bhat. , . Gandhinagar. ADITYA . Upgradation. with . Divertor. Configuration. Contributions from:. Deepti. Sharma . –. Equilibrium study (IPREQ). Richa. . Bandyopadhyay. . –. Transport simulation (TSC). Biagioni. On behalf of . SPARC_LAB. collaboration. ICFDT5. . 3–5 October 2018, LNF . Frascati. Angelo.Biagioni@lnf.infn.it. Outline. ICFDT5. . 3–5 October 2018, LNF . Frascati. Angelo.Biagioni@lnf.infn.it.