Technical Activities Report for April 1953 (open access)

Technical Activities Report for April 1953

Two xenon extraction runs were made this month. It appears that a small design change in Trap #2 will be necessary so that a dry ice-trichloroethylene slurry can be used for coolant rather than liquid freon. For each of the runs this month the enriched generator was exposed for four hours in the est pile operating at 100 watts. A period of eight hours for cooling and xenon builidup was allowed before the collection and separation runs were started.
Date: May 4, 1953
Creator: Faulkner, J. E.; Davenport, D. E. & Duvall, G. E.
System: The UNT Digital Library
The Identification of the Angular Inclusions Present in Rolled Uranium (open access)

The Identification of the Angular Inclusions Present in Rolled Uranium

Hanford uranium contains minute angular inclusions which affect the microstructure, reactivity, and other important factors controlling the serviceability of the metal. Small quantities of the inclusions have been isolated by chemical means, and the x-ray diffraction patterns and chemical analyses of the isolated materials have been determined. As a first step in the identification of the inclusions present in rolled uranium, a search was made for a chemical method of separating the inclusions from the matrix metal.
Date: May 15, 1953
Creator: Scott, F. A.
System: The UNT Digital Library
Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959. (open access)

Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.

Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
System: The UNT Digital Library
Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962 (open access)

Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962

Abstract: Progress is reported on research and development tasks under the Program Plan for Engineering Support and Development of Army Pressurized Water Reactor Power Plants, Contract AT(30-1)-2639, during the six months' period October 1, 1061 to March 31, 1962.
Date: May 25, 1962
Creator: Dixon, M. H.
System: The UNT Digital Library
Heat Transfer to Superheated Steam (open access)

Heat Transfer to Superheated Steam

Abstract: The physical property variation of superheated steam differs sufficiently from most other gases to warrant experimental investigation of heat transfer performance. Results are reported here of measurements made in a uniformly heated circular duct with steam at 1000 psi. The data agree very well with the expression use for design purposes, which is based on information in the literature for heating of other gases as well as steam. This work was a continuation of that performed under Task (Heat Transfer) of the Nuclear Superheat Project, AEC Contract AT(04-3)-189, Project Agreement 13.
Date: May 1963
Creator: Sutherland, W. A. (William Alan), 1931-
System: The UNT Digital Library
Nuclear Superheat Project. Internal Steam Separation Development of Radial Vane Steam Separators (open access)

Nuclear Superheat Project. Internal Steam Separation Development of Radial Vane Steam Separators

This technical report describes the development, design, operation, and performance of a full-circle, radial-vane steam separator for the boiling water section of a nuclear superheat reactor. Steam-water tests of this model have demonstrated that is has vane capacity in excess of that required for the 300-Mx(e) separate superheat reactor and for the 300-Mw mixed spectrum superheat reactor. It is proposed that the vane capacity requirement of the 600 Mw(e) separate superheat reactor may be attained by increasing the nozzle length.
Date: May 31, 1963
Creator: Moen, R. H.
System: The UNT Digital Library