PPT-Divertor
Author : kittie-lecroy | Published Date : 2017-04-16
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
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Divertor: Transcript
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. S Pitcher a C J Boswell J A Goetz B LaBombard B Lipschultz J E Rice and J L Terry MIT Plasma Science and Fusion Center NW17 Cambridge Massachusetts 02139 Received 18 November 1999 accepted 27 January 2000 The effect of divertor baf64258ing on Alcato L Adams X Bonnin JL Terry AYu Pigarov HA Scott and SI Krasheninnikov September 1998 email adamsmitedu Also at IV Kurchatov Institute of Atomic Energy Moscow Russian Federation Also at College of William and Mary Williamsburg VA Lawrence Livermore N 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 . SiC. -. Composite. Divertor. . X.R. Wang. 1. , S. Malang. 2. , M. S. Tillack. 1. . 1. University of California, San Diego, CA. 2. Fusion Nuclear Technology Consulting, Germany. ARIES-Pathways Project Meeting. 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. Divertor. . Concept – Pt 2 . Thomas L. Weaver: Platform Systems and Subsystems; BR&T. James B. Robinson: Reliability, Maintainability, and Testability; BCA. I-Li Lu: Applied Mathematics and Statistics; BR&T. 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. Configuration Design of the Fusion . Power Core . for. the ACT. (Draft). X.R. Wang. M.S. Tillack. S. Malang. Sept. 29, 2011. One sector (22.5 degree). ARIES-ACT 1B(Aggressive Physics), Posted at ARIES Web: June 8, 2011. . . 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. X.R. Wang, M. S. Tillack, . S. . Malang,. C. . Koehly. , F. . . Najmabadi. . and the ARIES Team. ARIES-Pathways Project Meeting. UC San Diego. January 22-23, 2013. Tasks and Assignments from Last ARIES Project Meeting . for NSTX-U. W.M. Davis. G. J. Tchilinguirian, . T. Carroll, K. G. Erickson, S. P. Gerhardt, P. Henderson,. . S. H. Kampel, P. Sichta, G. N. Zimmer. and the NSTX-U Research Team. NSTX-U. Supported by . 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.
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