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Title: 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}
}