METHOD FOR REPROCESSING MOLTEN FLUORIDE SALT REACTOR FUELS.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4627692
- Patent Number(s):
- 3677719
- Assignee:
- (to United States Atomic Energy Commission). TIC; NSA-26-058675
- NSA Number:
- NSA-26-058675
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-72
- Country of Publication:
- United States
- Language:
- English
- Subject:
- N40450* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing; BISMUTH; LIQUID METALS; MOLTEN SALT FUELS; PLUTONIUM; PROTACTINIUM; REDUCTION; REPROCESSING; SOLVENT EXTRACTION; SPENT FUELS; URANIUM; BISMUTH/solvent properties of liquids for plutonium and uranium; URANIUM/separation from spent protactinium-containing molten salt fuel by dual-temperature reductive extraction using molten bismuth; REACTOR FUELS/ reprocessing of spent protactinium-containing molten salt, by dual-temperature reductive extraction using molten bismuth; PLUTONIUM/separation from spent protactinium-containing molten salt fuel by dual-temperature reductive extraction using molten bismuth
Citation Formats
Whatley, M.E. METHOD FOR REPROCESSING MOLTEN FLUORIDE SALT REACTOR FUELS.. United States: N. p., 1972.
Web.
Whatley, M.E. METHOD FOR REPROCESSING MOLTEN FLUORIDE SALT REACTOR FUELS.. United States.
Whatley, M.E. Sat .
"METHOD FOR REPROCESSING MOLTEN FLUORIDE SALT REACTOR FUELS.". United States.
@article{osti_4627692,
title = {METHOD FOR REPROCESSING MOLTEN FLUORIDE SALT REACTOR FUELS.},
author = {Whatley, M.E.},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1972},
month = {1}
}
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