Tritium release and retention in beryllium and titanium beryllide after neutron irradiation up to damage doses of 23-38 dpa
Author:
Funder
Fusion for Energy
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference36 articles.
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2. High-temperature corrosion testing of titanium beryllides in the presence of water vapor and oxygen;Journal of Nuclear Materials;2024-11
3. Blistering Behavior of Beryllium and Beryllium Alloy under High-Dose Helium Ion Irradiation;Materials;2024-08-11
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