In-operando observation of helium-irradiation ion effects on surface deuterium retention through LiOH bonding in lithium films on tungsten substrates

The plasma surface interactions within a fusion device are one of the limiting factors to long pulse, power generating operation. A plasma facing component material will require effective heat tolerance, minimal erosion yield, and minimal fuel retention properties. Tungsten (W) has been selected as...

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Bibliographic Details
Main Authors: A.L. Neff, J.P. Allain
Format: Article
Language:English
Published: Elsevier 2019-05-01
Series:Nuclear Materials and Energy
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179118301972