作者: S.K. Lee , H.S. Kim , Bo-Hyun Chung , S.J. Noh
DOI: 10.1016/J.CAP.2011.05.005
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摘要: Abstract Tritium permeation is one of the key issues in fusion reactor operation. However, detailed data for hydrogen and its isotopes candidate materials are very limited. In order to investigate behaviors thin-solid materials, we constructed an experimental system adopting a continuous flow method; high vacuum 10 −9 Torr sample heating upto 1273 K were successfully achieved. Hydrogen experiments also performed by using samples stainless steel (SS 316L); results compared with previously existing reference data.