Retention properties in displacement damaged ultra-fine grain tungsten exposed to divertor plasma

One of the main advantages of using tungsten (W) as a plasma facing material (PFM) is its low uptake and retention of tritium. However, in high purity (ITER grade) W, hydrogenic retention increases significantly with neutron-induced displacement damage in the W lattice. This experiment examines an a...

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Bibliographic Details
Main Authors: J.L. Barton, D.A. Buchenauer, W.R. Wampler, D.L. Rudakov, Z.Z. Fang, C.J. Lasnier, J.A. Whaley, J.G. Watkins, E.A. Unterberg, R.D. Kolasinski, H.Y. Guo
Format: Article
Language:English
Published: Elsevier 2019-08-01
Series:Nuclear Materials and Energy
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179118301704