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Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department

Brookhaven National Laboratory Annual Report: July 1, 1960

Description: Report issued by the Brookhaven National Laboratory discussing the work conducted by the lab during the fiscal year of 1960. As stated in the introduction, "the progress and trends of the research program are presented together with a description of the operational, service, and administrative activities of the Laboratory" (p. vii). This report includes tables, illustrations, and photographs.
Date: April 1961
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department

Pilot Plant Preparation of Thorium Oxide and Thorium-Uranium Oxide During Fiscal Year 1960

Description: Test quantities of thoria (aporoximately 3800 lb of thorium oxide and 3200 lb of mixed thorium-uranium oxide) were prepared during FY-1960 for members of the Reactor Experimental Engineering Division (REED). For preparation of thorium oxide, the calcination temperature was varied from 650 to 1800 deg C. The surface area of the fired oxide ranged from 0.5 to 25 m/sup 2//g and the mean particle size ranged from 1 to 8 microns. For preparation of mixed thorium-- uranium oxide, the calcination temperature was varied from 1050 to 1225 deg C. The mixed oxide contained either 0.5, 3.0, or 8.0 wt.% of uranium as requested with a mean particle size of 1.5 microns. The over-all losses of thorium and uranium were 19.4 and 18.3%, re spectively. Four 1400 lb batches of thorium nitrate were dissolved to prepare solutions containing 300 to 350 g/liter of thorium for solvent extraction studies in the Chemical Technolcgy Division and 2100 lb of dry, recovered waste thorium oxide was supplied to the ORNL Fuel Cycle Program. (auth)
Date: July 29, 1960
Creator: Winget, R. H., Jr.
Partner: UNT Libraries Government Documents Department