Anodic behavior of uranium and zirconium during electrorefining spent fuel in molten salt.
Conference
·
OSTI ID:917672
No abstract prepared.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- NE; EM
- DOE Contract Number:
- DE-AC02-06CH11357
- OSTI ID:
- 917672
- Report Number(s):
- ANL/NT/CP-100069; TRN: US200817%%806
- Resource Relation:
- Conference: 8th International Conference on Nuclear Engineering (ICONE-8); Apr 2-6, 2000; Baltimore, MD
- Country of Publication:
- United States
- Language:
- ENGLISH
Similar Records
Molten salt separation from uranium during the processing of spent nuclear fuel.
Simplified Reference Electrode for Electrorefining of Spent Nuclear Fuel in High Temperature Molten Salt
Anodic process of electrorefining spent nuclear fuel in molten LiCl-KCL-UCl{sub 3}/CD system.
Conference
·
Tue Oct 30 00:00:00 EST 2001
·
OSTI ID:917672
Simplified Reference Electrode for Electrorefining of Spent Nuclear Fuel in High Temperature Molten Salt
Conference
·
Sat Sep 01 00:00:00 EDT 2007
·
OSTI ID:917672
Anodic process of electrorefining spent nuclear fuel in molten LiCl-KCL-UCl{sub 3}/CD system.
Conference
·
Wed Jul 03 00:00:00 EDT 2002
·
OSTI ID:917672