Abstract. A portion of the liquid-solid phase equilibrium region of the system U-UBr3 has been investigated by the method of thermal analysis. Uranium tribromide was prepared by introducing bromine vapor into a bulb containing finely divided uranium formed from the hydride. Cooling curves were obtained with tribromide and then with various compositions of tribromide and uranium. the information obtained showed that no solid sub halide exists but that the metal was soluble in the halide.

Abstract: "Temperatures above 400 C are required before reduction will take place with AH3. Above 500 C, a pyrophoric product was obtained. The chlorination temperature should be about 350 C initially and above 450 C at the end of the reaction to achieve 99% chlorination."

Although the results reported herein are rather encouraging and show the possibilities of utilizing flotation to increase recoveries and in some instances grades, they should not not be considered an optimum. As stated previously, time did not permit a detailed investigation of all reagents an conditions to obtain maximum grades and recoveries, but sufficient data, with enough typical samples, have been obtained to indicate a definite trend and encouragement for further studies. A comparison of the flotation results obtained with each of the samples is presented in Table 2.

The following report provides results taken from a sodium level indicator developed at Sacandaga using electrical resistance as the principle.

The following report provides the analysis of a large number of unreported data--taken during a study described in report HW-15230--containing density values obtained for solutions of uranium and nitric acid in tributyl phosphate-carbon tetrachloride solutions.

From introduction: "One of the most important factors which must be considered in the chemical processing of spent fuel elements is the safe and economic disposal of gaseous radioactive fission product wastes given off in the fuel element dissolution operation. For this reason work is underway at ORNL to study the various gas disposal methods that might be used to handle the radioactive fission product gases, krypton, xenon, and iodine."

The following report describes the usage of a semi-continuous ion exchange contactor--named the Higgins contactor--fit to operate the Purex process, a process that recovers plutonium and uranium from irradiated natural uranium fuel elements. It is intended to use the contactor in the final purification and concentration stage of the process plutonium streams.

Procedures for the separation and concentration of microgram to nanogram amounts of thallium from gram amounts to galena and meteorite metal, sulfide, and silicate phases were developed and are described. The thallium is extracted from aqueous bromide of chloride solutions of moderate acidity using diethyl ether. A device for elimination of the large volumes of solvent by dropwise evaporation is described. Organic matter in the residue is destroyed by treatment with aqua regia, and the thallium is the residue is converted to the nitrate for spectrochemical or mass-spectrometric examination. The presence of thallium in the residue is tested by Rhodamine B. test.

Program using the IBM-704 computer to calculate certain kinematic quantities for any non-relativistic reaction of the form.

Abstract. Methods of analysis for thorium, calcium, and nitric acid in solutions from thorium extraction purification columns are described and the results and errors are outlined. A brief description of methods of analysis that were not successful is included.

In homogeneous nuclear reactors significant quantities of radioactive inert gaseous fission products must be separated from the fuel solution for disposal. The present disposal scheme, which is employed on the HRT, is to pass the mixture of fission product gases and oxygen through a charcoal adsorption bed. the oxygen passes through the bed relatively un-adsorbed, but the radioactive inert gases are adsorbed and are displaced from the bed bed very slowly giving the gases a much greater residence time than would exist if no bed were used. This long residence or "holdup" time permits the short-lived inert gases to decay away before emission to the atmosphere and thus greatly reduces the safety hazard produced by disposal of the gases to the atmosphere. The same effect could be obtained by using a large holdup tank, but the charcoal bed is much more compact and thus required less shielding.

Certain solutions of the cylindrical wave-equation, such as the Possio integral, which are needed in the investigation of 2-dimensional weak-shocks are are determined in this paper.