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Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Description: Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs.
Date: December 1959
Creator: Salley, R. L. & Burt, W. R., Jr.

Manufacture of Fuel Plates for the Experimental Boiling Water Reactor

Description: From Abstract: "Discussed in the paper are the production of the uranium fuel alloy, the fabrication of the cladding components from Zircaloy-2 ingot, the assembly, welding, evacuation, and sealing of the cladding billets, the jacketing of the cladding billets with steel, and the roll bonding, heat treatment, stripping, and cleaning of the fuel plates. Evaluation of the fuel plates produced is also included."
Date: June 1957
Creator: Macherey, R. E.; Bean, C. H.; Carson, N. J., Jr. & Lindgren, J. R.

Resistance of Materials to Attack by Liquid Metals

Description: From Forward: "As their contribution, the Metallurgy Division of Argonne National Laboratory was asked to assemble all available unclassified and declassifiable data on the resistance of materials to attack by liquid metals. The resulting collation of data is contained in this report."
Date: July 1950
Creator: Kelman, LeRoy R.; Wilkinson, Walter D. & Yaggee, Frank L.

A Shielded Metallograph for Remote Metallography

Description: From Introduction: "This report presents the specific design requirements arising from these initial decisions, followed by description and keyed illustrations of the various features of the installation. The Bausch and Lomb Research Metallograph was the instrument chosen as being most readily adapted to the over-all plan."
Date: October 1957
Creator: Brown, F. L.; Haaker, L. W.; Paine, S. H. & Blomgren, R. A.

Terminal Report on the Mighty Mouse High-Flux Research Reactor Project

Description: From Introduction: "More specifically, it describes the basic reactor complex, the problems involved, the various approaches pursued, the present status and estimated cost of the project, along with recommendations for future research and development essential to the successful culmination of the project."
Date: September 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Dickson, R. F.; Heineman, J. B.; Kelber, C. N. et al.

Spectroscopy of Uranyl Salts in the Solid State

Description: From Introduction: "The interpretation of the fluorescence and absorption spectrum of the uranyl ion, indicated in this introduction, is based on the spectroscopic work of Nichols, Howes and co-workers (1914-1919), Dieke and van Heel (1925), Moerman and Kraak (1939), and Freymann and co-workers (1946-1948); on infrared studies (cf., Section 3 below) and Raman spectra; but most of all, on the work of Dieke, Duncan, and co-workers, carried out in 1943-1944 under the Manhattan District program. In the present chapter we will review briefly the earlier investigations in the field of uranyl salt and spectroscopy and give a somewhat more detailed summary of the results of Nichols and Howes and, particularly, of Dieke and co-workers."
Date: November 1953
Creator: Rabinowitch, Eugene

Roll Cladding Uranium-Zirconium and Uranium-Zirconium-Niobium Alloys with Zircaloy-2 for Plate-Type Fuel Elements

Description: From Abstract: "Investigations were made of alternate methods of bonding fuel shapes and the use of alternate core alloys in flat plates. Alternations and additions were made to development facilities needed to fabricate roll-clad plates for the EBWR core. Pilot production of EWBR-type plates proved that the plate cladding process could be adapted to production facilities."
Date: February 1958
Creator: Bean, C. H.; Macherey, R. E. & Lindgren, J. R.

Calculations on U235 Fission Product Decay Chains

Description: Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
Date: May 1952
Creator: Faller, I. L.; Chapman, T. S. & West, J. M.