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Actions for OXIDATION-REDUCTION REPROCESSING OF URANIUM CARBIDE REACTOR FUEL. II. BEHAVIOR OF PLUTONIUM AND FISSION PRODUCTS
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OXIDATION-REDUCTION REPROCESSING OF URANIUM CARBIDE REACTOR FUEL. II. BEHAVIOR OF PLUTONIUM AND FISSION PRODUCTS
Author
Smiley, W. G.
Published
United States : [publisher not identified], 1965.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1965.
Physical Description
microfiche : negative ; 11 x 15 cm
Full Text available online
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Report Numbers
NAA-SR-10738
Other Subject(s)
Cerium oxides
Chemistry
Diagrams
Electric arcs
Evaporation
Fission products
Fuels
Helium
Melting
Neodymium oxides
Numericals
Oxidation
Plutonium
Reduction
Reprocessing
Samarium oxides
Separation processes and procedures
Tables
Uranium carbides
Uranium oxides
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT(11-1)-GEN-8
NSA number: NSA-19-032282
OSTI Identifier 4591946
Research organization: Atomics International, Canoga Park, Calif.
View MARC record
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