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
Cited by: 3 works
Citation information provided by
Web of Science
Web of Science
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Investigation of Residual Anode Material after Electrorefining Uranium in Molten Chloride Salt
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Occlusion and ion exchange in the molten (lithium chloride + potassium chloride + alkaline earth chloride) salt + zeolite 4A system with alkaline earth chlorides of calcium and strontium, and in the molten (lithium chloride + potassium chloride + actinide chloride) salt + zeolite 4A system with the actinide chloride of uranium.
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Tue Dec 01 00:00:00 EST 2015
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OSTI ID:1252504
Anodic behavior of uranium and zirconium during electrorefining spent fuel in molten salt.
Conference
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Sat Jan 01 00:00:00 EST 2000
·
OSTI ID:1252504
Occlusion and ion exchange in the molten (lithium chloride + potassium chloride + alkaline earth chloride) salt + zeolite 4A system with alkaline earth chlorides of calcium and strontium, and in the molten (lithium chloride + potassium chloride + actinide chloride) salt + zeolite 4A system with the actinide chloride of uranium.
Journal Article
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Tue Apr 01 00:00:00 EST 2003
· Metall. Mater. Trans. B
·
OSTI ID:1252504