D retention in C- and O-contaminated tungsten during D+ irradiation
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference23 articles.
1. Recent Advances on Hydrogen Retention in ITER’s Plasma-Facing Materials: Beryllium, Carbon, and Tungsten
2. ITER Plant Description Document, Safety; Document No. G A0 FDR 1 01-07-13 545 R1.0, 2001 (Chapter 5).
3. Impacts of carbon impurities in hydrogen plasmas on tungsten blistering
4. Dynamic Behavior of Tungsten Surfaces due to Simultaneous Impact of Hydrogen and Carbon Ion Beam
5. C and D reemission from mixed W–C–D layers during single-species and simultaneous irradiations of W with C+ and D+
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2. Deuterium implantation into Y 2 O 3 -doped and pure tungsten: Deuterium retention and blistering behavior;Journal of Nuclear Materials;2017-04
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