ENGINEERING DEVELOPMENT STUDIES FOR MOLTEN-SALT BREEDER REACTOR PROCESSING NO. 7.

Author: McNeese, L. E.
Published: United States : [publisher not identified], 1972.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1972.
Physical Description: microfiche : negative ; 11 x 15 cm

Availability

Finding items...

Report Numbers

ORNL-TM-3257

Other Subject(s)

Breeder reactors
Column packing
Extraction columns
Films
Fission products
Fission products/separation from molten fluoride fuel by metal transfer
Fluorides
Fluorination
Fluorination/equipment for, frozen film thickness in induction heated
Laboratory equipment
Liquid metals
Molten salt breeder reactor/fuel reprocessing for, research progress on.
Molten salt fueled reactors
Molten salt fuels
N40450 -chemistry-radiochemistry & nuclear chemistry- reactor fuel processing
Packed columns/dispersions in, measurement of axial
Protactinium
Protactinium/separation from molten fluoride fuel by fluorination and reductive extraction
Rare earths
Rare earths/separation from molten fluoride fuel by fluorination and reductive extraction
Rare earths/separation from molten fluoride fuel by metal transfer
Reactor fuels/reprocessing of molten salt, fluorination- reductive extraction and metal transfer processes for
Reduction
Reprocessing
Separation processes
Solvent extraction
Uranium
Uranium/separation from molten salt fuel by reductive extraction

Collection

U.S. Atomic Energy Commission depository collection.

Note

DOE contract number: W-7405-ENG-26
NSA number: NSA-26-017635
OSTI Identifier 4662381
Research organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States).

View MARC record | catkey: 46150628