Rates and Mechanisms of the Loss of Fission Products from Uranium-Graphite Fuel Materials
- 1 March 1963
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 15 (3) , 288-295
- https://doi.org/10.13182/nse63-a26439
Abstract
Experimental evidence indicates that diffusion through the porous matrix and evaporation from the geometric surface are the rate-limiting processes in the loss of some fission products from uranium-graphite fuel. The loss of other fission products is rate-limited by unidentified processes which do not include those macroscopic diffusion or evaporation processes, but which may include diffusion or evaporation on the microscopic or granular scale.Keywords
This publication has 1 reference indexed in Scilit:
- Diffusion of Lanthanides and Actinides from Graphite at High TemperaturesNuclear Science and Engineering, 1961