High pulse number transient heat loads on beryllium

The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present fusion experiments, e.g. ASDEX Upgrade, it has been detected that up to 25% of the plasma energy loss is deposited in non divertor regions during edge localized mode (ELM) events. Therefore, the impact...

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Bibliographic Details
Main Authors: B. Spilker, J. Linke, Th. Loewenhoff, G. Pintsuk, M. Wirtz
Format: Article
Language:English
Published: Elsevier 2017-08-01
Series:Nuclear Materials and Energy
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179116300515