This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.

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.

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.

Report discussing progress made in testing methods for preparation of ductile zirconium by the National Research Corporation for the month of June, 1949.

The following report provides equations that result from a seminar in reactor physics.

Summary: Technical report describing the testing of eight Potter Meters, for metering inlet flow and measuring exit steam qualities in the Consumers Big Rock Point Instrumented Fuel Assemblies, were individually calibrated for flow and pressure drop up to 500 gpm in the low temperature (130 F) fluid flow facility. The flow calibration comparison made with an ASME orifice installation, agreed to within + - 1 percent among seven of the meters, and meter Serial No. 8 was 2.8 percent lower than the others. Pressure drop among the meters was within about 5 percent. Locked rotor pressure drop data was obtained on one meter. A fully instrumented fuel bundle was tested in the low temperature facility and pressure drop data obtained for the tieplates and meters, spacers, and channel rods. A mock-up of the exit end of the instrumented fuel bundles, composed of 1 foot of fuel rods, tieplate, and Potter Meter was tested in the High Pressure Heat Transfer Facility. Data was obtained for single- and two-phase calibration of total flow and exit steam quality in an instrumented bundle. Each meter was operated, for a minimum of 6-8 hours after bearing modifications necessitated by seizure of the rotors, in the …

Report issued by the Brookhaven National Laboratory discussing methods of processing reactor fuels such as uranium. As stated in the objective, "the primary objective of the project was to determine the effect of temperature, solution composition, and flow rate on the dissolving time for natural uranium slugs of varying history" (p. 2). This report includes tables, illustrations, and photographs.

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.