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).
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- 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}
}
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