Filters: Author is Mayer, M. [Clear All Filters]
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2010. Hydrogenic retention in irradiated tungsten exposed to high-flux plasma. Nuclear Fusion. 50:8. Abstract
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2011. Materials research under ITER-like divertor conditions at FOM Rijnhuizen. Journal of Nuclear Materials. 417:457-462. Abstract
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2011. Overview of ASDEX Upgrade results. Nuclear Fusion. 51:11. Abstract
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2003. Overview of JET results. Nuclear Fusion. 43:1540-1554.
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2011. Plasma surface interactions in impurity seeded plasmas. Journal of Nuclear Materials. 415:S19-S26. Abstract
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2013. Reduced deuterium retention in self-damaged tungsten exposed to high-flux plasmas at high surface temperatures. Nuclear Fusion. 53:043003. Abstract
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2012. Saturation of deuterium retention in self-damaged tungsten exposed to high-flux plasmas. Nuclear Fusion. 52:7. Abstract
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2011. TMAP7 simulations of deuterium trapping in pre-irradiated tungsten exposed to high-flux plasma. Journal of Nuclear Materials. 415:S636-S640. Abstract



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