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Loop-Type Liquid-Gas Separator

Description: The following report is a study of the separating qualities of a loop-type separator that can obtain separation with a smaller pressure drop.
Date: November 17, 1951
Creator: Barlow, J. W.; Jones, F. H. & Reuther, R. H.
Partner: UNT Libraries Government Documents Department

The System Zirconium-Iron-Tin. Status Report No. 4 for July 1, 1957- March 31, 1958

Description: A study of the solubility limits of iron and tin in alpha zirconium at temperatares below 500 deg C is in progress. Dilute alloys were prepared by arc- melting using the highest purity materials. Heat treatment of the alloys involves homogenizntion at 800 deg C followed by severe cold work prior to extended anneals at temperatures between 200 and 500 deg C in 50-degree intervals. Metallographic examination of annealed and quenched structures is the primary mode of investigation. Some magnetic susceptibility studies were also made. (auth)
Date: April 24, 1958
Creator: Tanner, L. E.
Partner: UNT Libraries Government Documents Department

HRE-2 DESIGN REPORT

Description: A manual is presented which describes the design of the Homogeneous Reactor Experiment No, 2 in detail and which provides references to the many reports pertaining to the design and development of components. The description of the design is limited to that existing before operation commenced, with parenthetical descriptions of improvements. (D.L.C.)
Date: March 1, 1964
Creator: Chapman, R.H.
Partner: UNT Libraries Government Documents Department

Aqueous Homogeneous Reactors for Producing Central-Station Power

Description: Report issued by the Oak Ridge National Laboratory discussing aqueous homogeneous reactors used in central-station power. As stated in the introduction, "it contains an evaluation of the potentiality of producing power only, as exhibited by aqueous homogeneous systems" (p. 6). This report includes tables, and illustrations.
Date: May 25, 1951
Creator: Briggs, R. B.; Haubenreich, P. N.; Sanders, J. P.; Aven, R. E.; Zapp, F. C.; Segaser, C. L. et al.
Partner: UNT Libraries Government Documents Department

A Homogeneous High Temperature Power Pile Utilizing Graphite Which Has Been Impregnated With Uranium

Description: Thermal reactors that have a significant fraction of fissioning occurring just above thermal energies are studied. First, the thermal neutron diffusion equation is corrected for fast fission effects. The resulting diffusion equation is shown to be equivalent to the Fermi Age equation corresponding to the same physical assumptions. Next, the one delayed neutron group kinetic equations for the corrected thermal flux are given, and the life time of the thermal neutron is corrected by the average slowing down time. (auth)
Date: August 23, 1946
Creator: Daniels, F.
Partner: UNT Libraries Government Documents Department