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Title: LIQUID--LIQUID REMOVAL OF PROTACTINIUM FROM SPENT MOLTEN SALT MIXTURES CONTAINING URANIUM TETRAFLUORIDE.

Inventors:
; ;
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4734351
Patent Number(s):
3472633
Assignee:
(to United States Atomic Energy Commission). DTIE; NSA-24-004361
NSA Number:
NSA-24-004361
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-70
Country of Publication:
United States
Language:
English
Subject:
N20510* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing; FUELS; PROTACTINIUM; REPROCESSING; SEPARATION PROCESSES; SOLVENT EXTRACTION; URANIUM TETRAFLUORIDE; REACTOR FUELS/reprocessing of molten fluoride, by liquid-liquid extraction; URANIUM FLUORIDES UF$sub 4$/separation of protactinium from molten, by liquid-liquid extraction; PROTACTINIUM/separation from spent molten fluoride fuels by liquid-liquid extraction

Citation Formats

McNeese, L.E., Watson, J.S., and Whatley, M.E. LIQUID--LIQUID REMOVAL OF PROTACTINIUM FROM SPENT MOLTEN SALT MIXTURES CONTAINING URANIUM TETRAFLUORIDE.. United States: N. p., 1969. Web.
McNeese, L.E., Watson, J.S., & Whatley, M.E. LIQUID--LIQUID REMOVAL OF PROTACTINIUM FROM SPENT MOLTEN SALT MIXTURES CONTAINING URANIUM TETRAFLUORIDE.. United States.
McNeese, L.E., Watson, J.S., and Whatley, M.E. Wed . "LIQUID--LIQUID REMOVAL OF PROTACTINIUM FROM SPENT MOLTEN SALT MIXTURES CONTAINING URANIUM TETRAFLUORIDE.". United States.
@article{osti_4734351,
title = {LIQUID--LIQUID REMOVAL OF PROTACTINIUM FROM SPENT MOLTEN SALT MIXTURES CONTAINING URANIUM TETRAFLUORIDE.},
author = {McNeese, L.E. and Watson, J.S. and Whatley, M.E.},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1969},
month = {1}
}