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Monex Process: Terminal Report
Chemical and engineering data were obtained for the feed digestion system and the extraction-scrub step of the Monex tributyl phosphate solvent-extraction process for recovering thorium and uranium from nitric acid-digested unclarified monasite sludge. Tests of the recommended conditions in a 2-in.-dia pulsed column demonstrated that thorium losses were approximately 1.2% and uranium losses, 1.5%. The flowsheet is workable but is not necessarily optimum.
Date:
January 31, 1958
Creator:
McNamee, R. J. & Wischow, R. P.
System:
The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date:
January 31, 1963
Creator:
Leitz, F. J.
System:
The UNT Digital Library
EVESR Nuclear Superheat Fuel Development Project: First Quarterly Report, May 4-August 31, 1962
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
Date:
January 31, 1963
Creator:
Pennington, R. T.
System:
The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1961
Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date:
October 31, 1961
Creator:
Oak Ridge National Laboratory. Health Physics Division.
System:
The UNT Digital Library