Injecting Irradiation Samples with a Uniform Concentration of Helium Using Curium-244
Author:
Affiliation:
1. Oak Ridge National Laboratory, Metals and Ceramics Division, P.O. Box X, Oak Ridge, Tennessee 37830
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT78-A26716
Reference8 articles.
1. Tritium diffusion in 304- and 316-stainless steels in the temperature range 25 to 222 °C
2. Surface effects on the diffusion of tritium in 304-stainless steel and zircaloy-2
3. Surface effects on tritium diffusion in niobium, zirconium and stainless steel
4. The determination of rare gas diffusion following recoil labelling of plane or spherical solids
5. J. L. BRIMHALL, Battelle-Pacific Northwest Laboratories, unpublished research.
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