Abstract. A satisfactory method has been found for dissolving thorium metal and thorium oxide in heat-treated 25-12 stainless steel vessels without excessive corrosion of the vessels. The dissolution medium consists of strong HNO3 containing a small amount of fluoride or fluo-silicate. the fluoride required has no harmful effects on a subsequent solvent-extraction step for a separation of uranium isotopes from the dissolved thorium.

Abstract: "Several chemical and physical characteristics of over seven hundred charges are computing with their performance in the process units. No correlation is attainable."

Abstract: Various procedures for extracting uranium from fiberglass air filters have been tested and compared. Satisfactory results which involve the least amount of handling are obtained by simply washing the material with hot 1:1 hydrochloric acid.

Abstract: In the NaF-UF4 system the following intermediate phases have been found: NaUF5, -Na2UF6, -Na2UF6 and NacUF7. NaLaF4 is the only intermediate phase observed in the system NaF-LaF3. In the course of an incomplete study of the system NaF-ThF4 the phases NaTh2F9, -Na2ThF6, -Na2ThF6 and Na4ThF8 have been observed. Crystal structure data are given for all the phases.

This report describes observations of a sample of Carbon-14, or radiocarbon, made using the method of mass spectrometry.

From abstract: "The distribution of carrier-free thorium, protoactinium and neptunium in the rat following intramuscular and oral administration has been studied. Oral adsorption for all three is negligible. Following parenteral administration, the skeleton is the organ showing the highest degree of prolonged and selective localization."

From abstract: "In an attempt to gain some insight into the physiological condition of mice surviving massive doses of radiation, a study of their vitality was undertaken. It was assured that the ability of these animals to do forced work would be a measure of their vitality, Stimulating exposed animals to run in exercise wheels to their fullest capacity, has resulted in a demonstration of a striking vitality less during a post-irradiative period, when no other effects are demonstrable by gross examination. Mice subjected to a medium-lethal dose of fast neutrons show a continuous vitality loss over a 300 day period following exposure. Control animals show no appreciable loss of vitality up to about 8 months of age, after which a gradual loss can be noted, probably due to a normal gereologic process."

This report describes a specific apparatus used to monitor the intensity of gamma radiation. The report includes a diagram of the apparatus.

From summary: "In previous project work, dilute mixtures of inorganic cations in aqueous solution have been concentrated by adsorption of the cations on a synthetic resin and they have been fractionated by selective desorption of the cations from the resin. In this report..the general procedure used in chemical separation, the equipment used, and the theory of the exchange equilibria and of the reaction rates are presented."

Abstract. The distribution coefficient of U(VI) between perchloric acid solutions and benzene solutions of TTA has been measured as a function of the acidity. It was possible to interpret the data in terms of the charge on the U(VI) species present in the aqueous phase. The experiments indicate that U(VI) exists as an ion charge +2 at acidities from 0.1M to 2.5M. In the interpretations of the distribution data, it was necessary to know the acidity coefficient of the uranyl chelate in the benzene solution. This was determined by measurement of the solubility of the compound UO2K2 - xH2). The activity coefficient of UO2K2 was found to decrease rapidly as the concentration of TTA in the benzene phase increased above 0.1M. This is probably due to the formation of a species involving more than two TTA molecules per U(VI)

Technical report describing the attempt to separate the long lived fission product oxides by volatilization methods. A fractionization crucible was used. The fractionations give a fair idea of the relative volatilities of the longer lived fission products and also of the degrees of separation of the plutonium oxide or oxides from the fission products.