Studies on the permeation of hydrogen and tritium in nuclear process heat installations
- 31 October 1975
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 34 (1) , 157-167
- https://doi.org/10.1016/0029-5493(75)90164-8
Abstract
No abstract availableKeywords
This publication has 11 references indexed in Scilit:
- Experiments for combining nuclear heat with the methane steam-reforming processNuclear Engineering and Design, 1975
- Formation and use of oxide films to impede outgassing of metalsJournal of Nuclear Materials, 1974
- Deuterium permeation through 309S stainless steel with thin, characterized oxidesJournal of Nuclear Materials, 1974
- Surface effects on tritium diffusion in niobium, zirconium and stainless steelJournal of Nuclear Materials, 1974
- Tritium diffusion in zircaloy-2 in the temperature range −78 to 204° CJournal of Nuclear Materials, 1974
- The Permeation of Hydrogen Isotopes through Structural Metals at Low Pressures and through Metals with Oxide Film BarriersNuclear Technology, 1974
- Surface effects on the diffusion of tritium in 304-stainless steel and zircaloy-2Journal of Nuclear Materials, 1973
- Tritium diffusion in 304- and 316-stainless steels in the temperature range 25 to 222 °CJournal of Nuclear Materials, 1972
- The diffusivity of tritium in 304 stainless steel in the temperature range 100° to 300°CMetallurgical Transactions, 1970
- Effect of Surface Treatment on the Corrosion of Stainless Steels in High-Temperature Water and SteamJournal of the Electrochemical Society, 1965