High-Z material erosion and its control in DIII-D carbon divertor

High-Z material erosion and its control in DIII-D carbon divertor

As High-Z materials will likely be used as plasma-facing components (PFCs) in future fusion devices, the erosion of high-Z materials is a key issue for high-power, long pulse operation. High-Z material erosion and redeposition have been studied using tungsten and molybdenum coated samples exposed in...

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Bibliographic Details
Main Authors: R. Ding, D.L. Rudakov, P.C. Stangeby, W.R. Wampler, T. Abrams, S. Brezinsek, A. Briesemeister, I. Bykov, V.S. Chan, C.P. Chrobak, J.D. Elder, H.Y. Guo, J. Guterl, A. Kirschner, C.J. Lasnier, A.W. Leonard, M.A. Makowski, A.G. McLean, P.B. Snyder, D.M. Thomas, D. Tskhakaya, E.A. Unterberg, H.Q. Wang, J.G. Watkins
Format: Article
Language:English
Published: Elsevier 2017-08-01
Series:Nuclear Materials and Energy
Online Access:http://www.sciencedirect.com/science/article/pii/S235217911630240X

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http://www.sciencedirect.com/science/article/pii/S235217911630240X

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