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Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date:
September 29, 1952
Creator:
Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
System:
The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."
Date:
September 29, 1952
Creator:
Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
System:
The UNT Digital Library
Aluminum Cladding Long Uranium Plates by Solid-State Bonding
From introduction: This report covers an investigation of solid-state bonding as a technique for aluminum cladding uranium plates of 3 by 0.180-in. cross section in lengths up to 14 ft.
Date:
March 29, 1955
Creator:
Saller, Henry A.; Dickerson, R. F. & Carlson, R. J.
System:
The UNT Digital Library
Further Studies with the GCRE Critical-Assembly
This report follows ciritical-assembly studies on: the effect on reactivity caused by changes in axial reflector materials; the effect on reactivity and the power perturbation caused by fast safety control-blade guides; the effect of changes in fuel-element material composition; the effect of changes in fuel-elements spacing designed to produce uniform radial power-generation rates.
Date:
December 29, 1958
Creator:
Dingee, David A.; Ballowe, William C.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
System:
The UNT Digital Library
Neutron-Flux Measurements in a Concentric-Cylinder Fuel Element
The following report presents neutron-flux measurements made with a concentric-cylinder element (Mark II) and includes axial, radial, and peripheral flux distributions.
Date:
January 29, 1959
Creator:
Anno, James N.; Fairand, Barry P. & Chastain, Joel W., Jr.
System:
The UNT Digital Library