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Title: METHOD FOR SEPARATING URANIUM, PROTACTINIUM, AND RARE EARTH FISSION PRODUCTS FROM SPENT MOLTEN FLUORIDE SALTS REACTOR FUELS.

Inventors:
; ;
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4019960
Patent Number(s):
3577225
Assignee:
(to United States Atomic Energy Commission).
NSA Number:
NSA-25-041903
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-71
Country of Publication:
United States
Language:
English
Subject:
N20510* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing; BISMUTH; FISSION PRODUCTS; FUELS; MELTING; MOLTEN SALT REACTORS; PROTACTINIUM; REDUCTION; REPROCESSING; SEPARATION PROCESSES; SOLVENT EXTRACTION URANIUM; BISMUTH/solvent properties of molten, for fission products, protactinium, and uranium from spent molten salt reactor fuels; PROTACTINIUM/separation from spent molten salt reactor fuels by selective reduction and extraction using molten bismuth; URANIUM/separation from spent molten salt reactor fuels by selective reduction and extraction using molten bismuth; FISSION PRODUCTS/separation from spent molten salt reactor fuels by selective reduction and extraction using molten bismuth; REACTOR FUELS/ reprocessing of molten salt, by selective reduction and extraction using molten bismuth

Citation Formats

Shaffer, J H, Moulton, D M, and Grimes, W R. METHOD FOR SEPARATING URANIUM, PROTACTINIUM, AND RARE EARTH FISSION PRODUCTS FROM SPENT MOLTEN FLUORIDE SALTS REACTOR FUELS.. United States: N. p., 1971. Web.
Shaffer, J H, Moulton, D M, & Grimes, W R. METHOD FOR SEPARATING URANIUM, PROTACTINIUM, AND RARE EARTH FISSION PRODUCTS FROM SPENT MOLTEN FLUORIDE SALTS REACTOR FUELS.. United States.
Shaffer, J H, Moulton, D M, and Grimes, W R. Fri . "METHOD FOR SEPARATING URANIUM, PROTACTINIUM, AND RARE EARTH FISSION PRODUCTS FROM SPENT MOLTEN FLUORIDE SALTS REACTOR FUELS.". United States.
@article{osti_4019960,
title = {METHOD FOR SEPARATING URANIUM, PROTACTINIUM, AND RARE EARTH FISSION PRODUCTS FROM SPENT MOLTEN FLUORIDE SALTS REACTOR FUELS.},
author = {Shaffer, J H and Moulton, D M and Grimes, W R},
abstractNote = {},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1971},
month = {1}
}