Modeling and analysis of a molten-salt electrolytic process for nuclear waste treatment

A pyrochemical processing has become one of the potential technologies for a future nuclear fuel cycle. An integrated multi-physics simulation and electrotransport model of a molten-salt electrolytic process are proposed and discussed with respect to the recovery of pure uranium when using thermoche...

Full description

Saved in:
Bibliographic Details
Published inJournal of radioanalytical and nuclear chemistry Vol. 280; no. 2; pp. 401 - 404
Main Authors Kim, K. R., Bae, J. D., Park, B. G., Ahn, D. H., Paek, S., Kwon, S. W., Shim, J. B., Kim, S. H., Lee, H. S., Kim, E. H., Hwang, I. S.
Format Journal Article
LanguageEnglish
Published Dordrecht Springer Netherlands 01.05.2009
Subjects
Chemistry
Chemistry and Materials Science
Diagnostic Radiology
Hadrons
Heavy Ions
Inorganic Chemistry
Nuclear Chemistry
Nuclear Physics
Physical Chemistry
Radioecology
Uranium Deposition
Uranium
Diffusion Boundary Layer
Diffusion Layer Thickness
Molten Salt
Online AccessGet full text

Cover

More Information
Summary:A pyrochemical processing has become one of the potential technologies for a future nuclear fuel cycle. An integrated multi-physics simulation and electrotransport model of a molten-salt electrolytic process are proposed and discussed with respect to the recovery of pure uranium when using thermochemical data. This study has been performed to provide information for diffusion boundary layers between the molten salt (KCl-LiCl) and electrode. The diffusion-controlled electrochemical model demonstrate a prediction of the electrotransport behaviors of LWR spent fuel as a function of the time up to the corresponding electrotransport satisfying a given applied current based on a galvanostatic electrolysis.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-009-0534-4