Filling Instructions for the Pratt & Whitney Forced Convection Liquid Metal Inpile Loop Experiment (PW19) (open access)

Filling Instructions for the Pratt & Whitney Forced Convection Liquid Metal Inpile Loop Experiment (PW19)

The apparatus and procedures that are to be used to fill the liquid metal system of the Pratt and Whitney Forced Convection Liquid Metal Inpile Loop are described. The liquid metal to be used is a mixture containing 56% Na and 44% K, which is a liquid at room temperature. In order to simplify the filling procedure at the reactor site, two containers, each of which contains exactly enough liquid metal to fill the experiment to the prescribed level, a fill dolly incorporating a purified helium system, and an evacuation system will be provided at the reactor site. After completion of the liquid metal transfer, the liquid metal fill tube will be crimped, cut, and seal welded. The liquid metal and helium systems will then be pressurized through the helium fill tubes, which will also be crimped, cut, and seal welded. Each tube seal weld will be inspected after completion of the weld by mass spectrometry leak check and dye penetrant fault detection
Date: April 29, 1959
Creator: Heyl, P. T.
System: The UNT Digital Library
Fabrication of Beryllium: a Bibliography (open access)

Fabrication of Beryllium: a Bibliography

This bibliography contains 147 references on the fabrication of beryllium. References are also given on the brazing, casting, cladding, extrusion and welding of beryllium and some beryllium-rich alloys. The bibliography is limited to the period 1950 - 1959. references are arranged alphabetically by title, with author and subject indexes provided. Sources used in compiling this bibliography are: Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program - Classified and Unclassified Versions, Engineering Index, Nuclear Science Abstracts, TISE, List of Bibliographies in the Atomic Energy Program.
Date: April 1, 1960
Creator: Cernak, Elizabeth A.
System: The UNT Digital Library
The Thermal Expansion of Thirteen Tungsten Carbide Cermets from 68 to 1800 F (open access)

The Thermal Expansion of Thirteen Tungsten Carbide Cermets from 68 to 1800 F

The linear thermal expansion of thirteen tungsten carbide cermets with cobalt binder was investigated experimentally over the temperature range from 68 to 1800 F. Cobalt contents varied from 2.5 to 60 per cent. Several compositions included additions of mixed carbides of titanium, tantalum, and columbium. The experimentally observed coefficients of thermal expansion for the various compositions were compared with coefficients analytically computed from the coefficients for the constituents. Three such analytical methods were evaluated. In one method, the coefficient of expansion of the mixture was computed by volume fractions and in a second method by weight fractions. In the third method, the computation accounted for the stresses set up in the mixture by the difference in thermal expansion of the carbide skeleton and the cobalt binder. The expansions of all these cermets agreed with the values computed by weight fractions or by the stress method within 12 per cent, and by volume fractions within 28 per cent. The cermets containing less than one per cent mixed carbides agreed with the expansion computed either by weight fractions or by stress within 8 per cent, the cermets containing more than five per cent mixed carbides agreed with values computed by volume fractions …
Date: April 26, 1963
Creator: Harrington, L. C. & Rowe, G. H.
System: The UNT Digital Library
The Thermal Conductivity of Uranium Monocarbide (open access)

The Thermal Conductivity of Uranium Monocarbide

Uranium carbide shows promise as a fuel material for reactors operating at relatively high temperatures based on its high melting point, high uranium density and high thermal conductivity. Before refined reactor designs can be made, however, good quantitative data on the thermal conductivity at temperatures in excess of 1000C is required. This technical report presents data gathered as part of a continuing study aimed at determining the thermal conductivity of refractory uranium fuels as a function of temperature, density and composition over the temperature range 1000-2200C. At the inception of this program it was felt that an absolute method capable of achieving high temperatures was necessary and that the difficulties encountered in fabricating the large complex specimens needed were justified. The steady state radial heat flow method and apparatus of Rasor and McClelland were therefore chosen. The technical report discusses the experimental equipment and presents results of measurements on three specimens of UC over a temperature range 900 to 1600C. An analysis of the data is made with respect to other physical properties of the material and the measured conductivities are compared with the work of other investigators.
Date: April 2, 1964
Creator: Sobon, J. T.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
System: The UNT Digital Library
Radiation Effects on Aluminum, Elastomers, and Lubricants: a Bibliography (open access)

Radiation Effects on Aluminum, Elastomers, and Lubricants: a Bibliography

This bibliography contains 145 references on radiation effects on aluminum, elastomers, and lubricants. Also included are references on radiation units and conversion factors. The bibliography is limited to the period 1950 through 1959, with the references arranged alphabetically by title in five categories. An author index is provided. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Bibliographies of Interest to the Atomic Energy Program: Classified and Unclassified Versions, Monthly List of Bibliographies in the Atomic Energy Program. U.S.A.E.C. Technical Information Service Extension, Nuclear Science Abstracts.
Date: April 4, 1960
Creator: Cernak, Elizabeth A.
System: The UNT Digital Library
Hydrides of Titanium, Yttrium, and Zirconium: a Bibliography (open access)

Hydrides of Titanium, Yttrium, and Zirconium: a Bibliography

This bibliography contains 94 references on metal hydrides, with particular emphasis placed on the hydrides of titanium, yttrium, and zirconium. The bibliography covers the period 1955 through 1959. The references are arranged alphabetically by title. Sources used in compiling this bibliography are: Applied Science and Technology Index, Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program, Classified and Unclassified Parts, Industrial Arts Index, Internal Card Catalog, Monthly List of Bibliographies in the Atomic Energy Program, U.S.A.E.C. Technical Information Service Extension, Nuclear Science Abstracts.
Date: April 28, 1960
Creator: Cernak, Elizabeth A.
System: The UNT Digital Library