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Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress are presented. This report includes tables, illustrations, and photographs.
Date: 1962
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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MUFT Revision : A Fast Neutron Spectrum Code for the IBM-650

Description: Report documenting the MUFT-R program, which is "designed to solve the fast neutron transport problem for general mixtures of elements and obtain sets of average fast neutron diffusion constants for specified portions of the fast energy spectrum" (p. iii). Includes detailed derivations of utilized equations.
Date: 1962
Creator: Grimesey, Robert A.; Mullen, Frank Edward & Gannon, L. J.
Partner: UNT Libraries Government Documents Department
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Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1961 - March 1, 1962

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: April 1, 1962
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Partner: UNT Libraries Government Documents Department
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U.S. Atomic Energy Commission Idaho Operations Office Health and Safety Division Annual Report: 1961

Description: Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS).
Date: May 21, 1962
Creator: U.S. Atomic Energy Commission. Idaho Operations Office.
Partner: UNT Libraries Government Documents Department
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Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels

Description: Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.
Date: June 20, 1962
Creator: Chamberlain, H. V.
Partner: UNT Libraries Government Documents Department
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