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Title: Investigation of residual anode material after electrorefining uranium in molten chloride salt

Journal Article · · Journal of Nuclear Materials

Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
Grant/Contract Number:
AC02-06CH11357
OSTI ID:
1252504
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 467 Journal Issue: P2; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
Netherlands
Language:
English
Citation Metrics:
Cited by: 3 works
Citation information provided by
Web of Science

References (6)

Behavior of U-Zr Alloy Containing Simulated Fission Products during Anodic Dissolution in Molten Chloride Electrolyte journal March 2010
Determining the Exchange Current Density and Tafel Constant for Uranium in LiCl/KCl Eutectic journal October 2014
Modeling of anodic dissolution of U–Pu–Zr ternary alloy in the molten LiCl–KCl electrolyte journal February 2005
Development of Treatment Process for Anode Residue from Molten Salt Electrorefining of Spent Metallic Fast Reactor Fuel journal March 2013
Experimental investigations and thermodynamic modelling of KCl–LiCl–UCl3 system journal June 2014
Investigation of a LiCl–KCl–UCl3 system using a combination of X-ray diffraction and differential thermal analyses journal October 2013