Diffusion coefficients of cesium in un-irradiated graphite and comparison with those obtained from in-pile experiments
- 1 December 1989
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 168 (3) , 328-336
- https://doi.org/10.1016/0022-3115(89)90599-0
Abstract
No abstract availableKeywords
This publication has 7 references indexed in Scilit:
- In-pile release behavior of metallic fission products in graphite materials of an htgr fuel assemblyJournal of Nuclear Materials, 1987
- Distribution of fission products in irradiated graphite materials of HTGR fuel assemblies: Third and fourth OGL-1 fuelsJournal of Nuclear Materials, 1985
- Distribution of fission and activation products in the graphite sleeves of HTGR fuel rods: first and second OGL-1 fuelsJournal of Nuclear Materials, 1983
- Diffusion of cesium through graphiteJournal of Nuclear Materials, 1976
- Laboratory determinations of strontium diffusion coefficients in graphiteJournal of Nuclear Materials, 1976
- The Compatibility of Graphite with CesiumNuclear Science and Engineering, 1967
- Diffusion of Nonvolatile Metallic Elements in GraphiteJournal of Applied Physics, 1965