Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.

The following report follows a correction on a previous report (CP-1381) on the value of the magnitude of the gamma effect.

This preliminary report follows the investigation on the determination of thermal neutron flux in water by the foil method.

This report describes the Temple Mountain district in Utah, specifically four Shinarump-capped areas that are recommended for ore mining.

Discussing recommendations for wagon drilling in the Temple Mountain District, Utah

Cost estimates for two types of Th producing plants are offered. One utilizes Th(NO3)4 as raw material, the other uses monazite sand. Final processing schemes and plant designs are not fixed, so the estimates represent maximum costs. Recommendations for research and development of Th producing methods are given.

From abstract: The estimation of beryllium oxide in beryllium metal depending on the differential solubilities of the two material in dilute hydrochloric acid is presented. The results compare favorably with the present beryllium chloride volatilization procedure. Alternate methods are described, and the limitations and possible errors are discussed.

From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."

Report discussing improved methods of isolating and producing curium, as well as its density, the absorption spectrum of Cm⁺³, and the molar magnetic susceptibility of CmF₃.

Calculations indicative of the power loss for 75 in.radius gap splitters are given.

Technical report outlining the fabrication of twenty-five fuel assemblies and three shim-safety rod fuel sections for use in the Materials Resting Reactor Mock-Up Critical Experiments. Results show that two of the assemblies exceeded tolerance in a few of the key dimensions, but were considered acceptable and as a consequence, production was carried out with no rejects. [From Abstract]

Report discussing methods for preparing various protactinium compounds, including protactinium oxides, tetrafluoride, and oxysulfide. Additionally, a method for making the protactinium metal is mentioned.

Calculations presented were done to determine what maximum temperature gradients and stresses would be in typical designs of flat thorium plates, 100 mils thick and coolled on both sides by NaK.

From introduction: A trip into the Henry Mountains area occupied the days from March 6 to 9, 1951, inclusive, excepting March 7, which was used to examine Reo Hunt's deposit in Poison Spring Wash. Observations were made on stratigraphy, regional geology, and the locations of the known deposits of uranium and vanadium.

The trip into the Henry Mountains Area used to examine the Reo Hunt's deposit s of uranium and vanadium.

Monthly report of the U.S. Geological Survey's trace element investigations including an outline of field work, laboratory work, and staff activities that have been completed or are in process.

Abstract: A comprehensive study was made of various fractionation systems for the fractional separation of barium-radium mixtures. The most efficient and simplest fractionation scheme was chosen on the basis of the thermodynamics of separating the constituents of mixed crystals and of the combining fractions in a system of repeating composition. This scheme was applied to the separation of barium and radium by utilizing the countercurrent batch fractionation of the chromates. The chromate procedure was evaluated by a comparison with the classic methods which employ the fractional crystallization of the halides. The chromate method is more practical on the basis of radium enrichment per fractionation step, control of precipitating conditions, simplicity, and speed of operation.

Abstract: A systematic investigation has been made of the physical and mechanical properties of dilute alloys of oxygen in high-purity iodide-refined zirconium. A marked strengthening effect was observed as a result of oxygen additions. Results of tensile tests at elevated temperatures up to 400°C are also presented. Preparation of alloys is discussed in detail.