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Title: METHOD FOR REPROCESSING SPENT MOLTEN SALT REACTOR FUELS.

Inventors:
;
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4645513
Patent Number(s):
3672846
Assignee:
(to United States Atomic Energy Commission). TIC; NSA-26-053086
NSA Number:
NSA-26-053086
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 REACTORS; MOLTEN SALTS; NUCLEAR FUELS; PROTACTINIUM; RARE EARTHS; REPROCESSING; SEPARATION PROCESSES; SOLVENT EXTRACTION; SPENT FUEL ELEMENTS; URANIUM; RARE EARTHS/separation from spent molten salt fuel by reductive extraction; REACTOR FUELS/reprocessing of molten salt, by fluorination and reductive extraction methods; PROTACTINIUM/separation from spent molten salt fuel by reductive extraction; REACTORS, MOLTEN-SALT/fuel reprocessing for, by fluorination and reductive extraction methods; URANIUM/separation from spent molten salt fuel by fluorination and reductive extraction methods

Citation Formats

McNeese, L.E., and Ferguson, D.E. METHOD FOR REPROCESSING SPENT MOLTEN SALT REACTOR FUELS.. United States: N. p., 1972. Web.
McNeese, L.E., & Ferguson, D.E. METHOD FOR REPROCESSING SPENT MOLTEN SALT REACTOR FUELS.. United States.
McNeese, L.E., and Ferguson, D.E. Sat . "METHOD FOR REPROCESSING SPENT MOLTEN SALT REACTOR FUELS.". United States.
@article{osti_4645513,
title = {METHOD FOR REPROCESSING SPENT MOLTEN SALT REACTOR FUELS.},
author = {McNeese, L.E. and Ferguson, D.E.},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1972},
month = {1}
}