MOLTEN-SALT BREEDER REACTOR FUEL PROCESSING
- Author
- McNeese, L. E.
- Published
- [Place of publication not identified] : [publisher not identified], 1972.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1972. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Ferris, L. M. and Nicholson, E. L.
- Report Numbers
- CONF-720522-3
- Other Subject(s)
- Alkaline earth metals
- Alkaline earth metals/separation from msbr fuel by metal transfer process
- Breeder reactors
- Fluorination
- Liquid metals
- Molten salt breeder reactor/fuel reprocessing for, research progress on.
- Molten salt fuels
- Molten salt reactors
- N40450 -chemistry-radiochemistry & nuclear chemistry- reactor fuel processing
- Protactinium
- Protactinium/separation from msbr fuel by reductive extraction
- Rare earths
- Rare earths/separation from msbr fuel by metal transfer process
- Reactor fuels/reprocessing of molten salt, by fluorination, reductive extraction, and metal transfer
- Reprocessing
- Separation processes
- Solvent extraction
- Spent fuels
- Uranium
- Uranium/separation from msbr fuel by fluorination, continuous
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- NSA number: NSA-26-038332
OSTI Identifier 4628558
Research organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States).
View MARC record | catkey: 43359574