DEVELOPMENT OF AQUEOUS PROCESSES FOR FAST REACTOR FUELS.

Technical Report · Fri Oct 30 23:00:00 EST 1970

OSTI ID:4748172

• Research Organization: Oak Ridge National Lab., Tenn.
• NSA Number: NSA-24-000267
• OSTI ID: 4748172
• Report Number(s): ORNL--4422
• Country of Publication: United States
• Language: English

Related Subjects

ABUNDANCE
AIR
AMINES
BUTYL PHOSPHATES
COMPUTER PROGRAMS/ORIGEN
for calculation of transient concentrations of nuclides
COMPUTERS
CRITICALITY
ECONOMICS
FAST NEUTRONS
FUEL CANS
FUELS
IODINE
IODINE/separation from irradiated oxide fuels
head- end treatment for
KRYPTON
LIQUID METAL FAST BREEDER REACTOR/fuels for
criticality calculations for equipment for reprocessing of
LIQUID METAL FAST BREEDER REACTOR/fuels for
reprocessing and transport of
LMFBR
N20510* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing
N38700 --Reactor Components
Fuels & Accessories
NUCLEI
PLUTONIUM
PLUTONIUM OXIDES
PLUTONIUM OXIDES PuO$sub 2$/PuO$sub 2$--UO$sub 2$
dissolution of stainless steel-clad
PLUTONIUM/ separation from irradiated fuels by solvent extraction using TBP
PLUTONIUM/separation from irradiated stainless steel-clad plutonium dioxide--uranium dioxide fuel
PROGRAMMING
RADIOCHEMICAL PROCESSING PLANTS/criticality calculations for
REACTOR FUELS/ reprocessing by TBP pro
REACTOR FUELS/reprocessing of oxide
material balance flowsheets for
REACTORS
REPROCESSING
SAFETY
SEPARATION PROCESSES
SHIELDING
SOLUBILITY
SOLVENT EXTRACTION
STAINLESS STEELS
TBP
TRANSPORT
TRITIUM
URANIUM
URANIUM DIOXIDE
URANIUM OXIDES UO$sub 2$/PuO$sub 2$--UO$sub 2$
dissolution of stainless steel-clad
URANIUM/ separation from irradiated fuels by solvent extraction using TBP
XENON
XENON/separation from irradiated oxide fuels
head-end treatment for