Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Oklahoma City Quadrangle, Oklahoma: Appendix C

Data collected as part of hydrogeochemical and stream sediment reconnaissance data for Oklahoma City NTMS quadrangle including laboratory data on well water, spring water, and stream sediments as well as field data.
Date: July 26, 1978
Creator: National Uranium Resource Evaluation Program
Object Type: Dataset
System: The UNT Digital Library
Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Oklahoma City Quadrangle, Oklahoma (open access)

Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Oklahoma City Quadrangle, Oklahoma

From abstract: Results of a reconnaissance geochemical survey of the Oklahoma City Quadrangle, Oklahoma are reported. Field and laboratory data are presented for 812 groundwater samples and 847 stream sediment samples. Statistical and areal distributions of uranium and other possibly uranium-related variables are displayed. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed.
Date: July 26, 1978
Creator: National Uranium Resource Evaluation Program
Object Type: Report
System: The UNT Digital Library
Advanced Seminar in Reactor Physics (open access)

Advanced Seminar in Reactor Physics

The following report provides equations that result from a seminar in reactor physics.
Date: July 26, 1950
Creator: Smith, Nicholas M.
Object Type: Report
System: The UNT Digital Library
Emission Rate of Fission Products from a Hole in the Cladding of a Reactor Fuel Element (open access)

Emission Rate of Fission Products from a Hole in the Cladding of a Reactor Fuel Element

It is assumed that when a hole appears in the cladding of a reactor fuel tube the fission products in the space between the fuel and the cladding will diffuse towards the hole. There they are swept away by the flow of steam past the hole. The process of diffusion is assumed to be governed by the ordinary diffusion equation with the boundary condition that the density of the fission products is zero at the surface of the hole. The diffusion equation is solved for the case of steady-state emission for a number of geometrical arrangements: long slit in plane surface; long slit in cylindrical surfaces circular hole in plane surface; circular hole in cylindrical surface; hole at end of cylindrical fuel rods and diffusion space of variable thickness. The time dependent solution of the diffusion equation is also found for a planar diffusion space. The effect of a temperature gradient is discussed.
Date: July 26, 1956
Creator: Helstrom, Carl W.
Object Type: Report
System: The UNT Digital Library