From abstract: "An electrolytic refining process was developed to produce tritium of high isotopic purity with negligible loss. The operation is semicontinuous, with multiple stages in cascade. All tritium oxide is handled within the confines of a hermetically sealed enclosure. The mechanical operability of the process was demonstrated in a five-stage prototype line designed to process 15 gram-mols of feed per day. An average separation factor per stage of 5.3 was obtained with a feed of tracer-level tritium. The equipment is described in detail."

From abstract: "The distribution of uranyl nitrate was measured from aluminum nitrate and nitric acid solutions into diluted tri-n-butyl phosphate. This information is useful for designing solvent extraction processes for recovery of uranium from aluminum nitrate or nitric acid solutions."

From abstract: "The combined attack of HNO3 and HNO2 on tributyl phosphate - kerosene solvent used in the Purex process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination."

From introduction: "In previous work on the ion exchange adsorption of ruthenium, it was observed that when certain compounds of sulfur were added to dilute uranyl nitrate solutions, precipitates formed which carried ruthenium. The purpose of this investigation was to develop a similar method for scavenging ruthenium from concentrated uranyl nitrate solutions. Such a method, combined with the silica gel treatment for removing zirconium and niobium, might provide an integrated process to remove all three contaminants."

From abstract: "Background material leading to the development of the metal quality of reactor-grade thorium is given. The metal should be sound and of uniform hardness, free of internal cracks and inclusions, and corrosion resistant. It should contain only small amounts of natural uranium, thorium oxide, and elements that act as reactor poisons. Because of their effect upon metal quality, various methods for the production of thorium are discussed. Use of consumable electrode arc melting as the final step has contributed much to the production of thorium of excellent quality for reactor use."

From abstract: "Essentially void-free fusion-type joints of high strength were produced between small specimens of Type M-276 sintered aluminum powder plate and 1100 Hl4 wrought plate, using a technique consisting of controlled and brief exposure of the ends of both materials to an ultrasonically active coupler face in a bath of molten 1100 aluminum, followed immediately by butt joining and fast cooling. With further development, the process should be adaptable to other types of sintered aluminum powder materials and to other joint geometries."

From abstract: "Calculations are made of the magnitude of the radiation bursts that can occur in a mixer-settler and in a large tank containing U235 solution if the concentration gets out of control. Various rates of increase in concentration are studied and various restraints are imposed on the expansion of the systems. The neutron kinetics equations, with five groups of delayed neutrons, and the equations relating the neutron flux to the pressure and volume of the gas formed by fission fragments are combined into a single first-order nonlinear differential matrix equation which is solved numerically on the IBM 650. In a mixer-settler containing 9.7 kg of U235 the magnitude of the burst was calculated to be about 10^17 fissions, both for low rates of increase in reactivity (<[or equal to]0.01% per sec) regardless of the confinement, and for an unconfined system regardless of the rate of increase reactivity. In a tank containing 88.9 kg of U235 successive bursts of about 10^19 fissions were calculated to occur about 0.5 second apart when the rate of increase in reactivity was about 0.1% per second."

From Abstract: "Fuel tubes of enriched uranium-aluminum alloy were melted to various degrees of severity in the SPERT I reactor as a part of a program to evaluate reactor operating hazards. The heat flux encountered during the tests ranged from 200,000 to 650,000 pcu/(hr)(ft^2). The time required for the metal temperature to reach the melting point from the time when burnout began varied from 1.3 to 4.9 seconds. During these tests, pressure pulses were produced at a frequency of about one per second with peaks of about 150 psi."