ENGINEERING DEVELOPMENT STUDIES FOR MOLTEN-SALT BREEDER REACTOR PROCESSING NO. 1.

Author: McNeese, L. E.
Published: United States : [publisher not identified], 1970.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1970.
Physical Description: microfiche : negative ; 11 x 15 cm

Availability

Finding items...

Report Numbers

ORNL-TM-3053

Other Subject(s)

Chemical reactions
Computer programs/matador, for material-balance calculations for molten salt breeder reactor
Computers
Electrolytic cells
Electrolytic cells/development for reprocessing of msbr fuel by reductive extraction
Fuels
Fused salt fuel
Molten salt breeder reactor/fuel reprocessing for
Molten salt breeder reactor/fuel stream of, computer program for calculation of chemical, nuclear, and physical processes in.
Msbr
N20510 -chemistry-radiochemistry & nuclear chemistry- reactor fuel processing
N38150 -power reactor development-fuels
Nuclear reactions
Programming
Rare earths
Rare earths/separation from thorium in bismuth solution by fractional crystallization
Reactor fuels/reprocessing of msbr, semicontinuous engineering experiments on reductive extraction for
Reduction
Reprocessing
Separation processes
Solvent extraction
Thorium
Thorium/separation from rare earths in bismuth solution by fractional crystallization

Collection

U.S. Atomic Energy Commission depository collection.

Note

DOE contract number: W-7405-ENG-26
NSA number: NSA-25-004138
OSTI Identifier 4088988
Research organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States).

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