MIXING AND SETTLING SEPARATION PROCESS FOR URANIUM OR PLUTONIUM.
Patent
·
OSTI ID:4627689
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-26-058678
- Assignee:
- (to United States Atomic Energy Commission).
- Patent Number(s):
- US 3677743 .
- OSTI ID:
- 4627689
- Country of Publication:
- United States
- Language:
- English
Similar Records
PROCESS OF SEPARATING PLUTONIUM FROM URANIUM
PROCESS FOR SEPARATING PLUTONIUM FROM URANIUM
PROCESS FOR THE SEPARATION OF PLUTONIUM FROM NEUTRON IRRADIATED URANIUM
Patent
·
1958
·
OSTI ID:4262026
PROCESS FOR SEPARATING PLUTONIUM FROM URANIUM
Patent
·
1959
·
OSTI ID:4164865
PROCESS FOR THE SEPARATION OF PLUTONIUM FROM NEUTRON IRRADIATED URANIUM
Patent
·
1960
·
OSTI ID:4116743
Related Subjects
FISSION PRODUCTS
FISSION PRODUCTS/separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers
LIQUID METALS
MIXER-SETTLERS
MOLTEN SALTS
N40450* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing
PLUTONIUM
PLUTONIUM OXIDES
PLUTONIUM/separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers
REACTOR FUELS/reprocessing of mixed oxide, by solvent extraction using liquid metals, molten salts, and mixer--settlers
SOLVENT EXTRACTION
SPENT FUELS
URANIUM
URANIUM DIOXIDE
URANIUM/ separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers
FISSION PRODUCTS/separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers
LIQUID METALS
MIXER-SETTLERS
MOLTEN SALTS
N40450* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing
PLUTONIUM
PLUTONIUM OXIDES
PLUTONIUM/separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers
REACTOR FUELS/reprocessing of mixed oxide, by solvent extraction using liquid metals, molten salts, and mixer--settlers
SOLVENT EXTRACTION
SPENT FUELS
URANIUM
URANIUM DIOXIDE
URANIUM/ separation from spent oxide fuels by solvent extraction using liquid metals, molten salts, and mixer-settlers