A new gas-liquid countercurrent system (the ANCO system from Anisole-Complex) for the enrichment of boron isotopes has been developed. It is believed that use of this systems will result in a considerably lower unit cost for enriched boron-10 than was previously possible. The system utilizes the exchange reaction between BF3 (gas) and BF3·anisole (liquid) to concentrate boron-10 in the liquid phase. The single stage isotopic separation factor for this system has been found to vary from 1.039 at 0°C to 1.029 at 30°C. The isotopic exchange reaction has been shown to be rapid. Vapor pressures of the complex as a function of temperature have been measured and the heat of formation of the complex determined. Laboratory experiments show that quantitative removal of the BF3 from the complex can be accomplished by heating. A complete miniature ANCO plant was constructed and operated in the laboratory to test the feasibility of the system. The system was found to operate efficiently with a minimum of attention, and to enrich the isotopes of boron as expected. Based upon the experience obtained with the laboratory ANCO unit, a pilot plant large enough to utilize a 6-inch diameter exchange column was designed. The design calculations of …

The enthalpies and heat capacities of seventeen fluoride mixtures in the liquid state have been determined using Bunsen Ice Calorimeters and copper block calorimeters. The fluoride mixtures were composed of the fluorides of two or more of the following metals: lithium, sodium, potassium, beryllium, zirconium, and uranium. The enthalpies and heat capacities of most of these mixtures were studied in the solid state also. Estimates of the heat of fusion have been made. General empirical equations have been developed which represent the enthalpies and heat capacities of the fluoride mixtures in the liquid and in the solid state.

Technical report covering chemistry of source, fissionable, and structural elements, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, and instrumentation at the Oak Ridge National Laboratory for the period ending September 30, 1950. [From Abstract]

From abstract: "This report presents the progress in the laboratory development of a continuous solvent recovery process for the tributyl phosphate-diluent mixture used in the Purex Process. Investigations were made with 1/2" diameter pulse columns, using a nine foot sodium carbonate contacting column and a four foot water wash column."

From abstract: "The following report presents a summary of operating experience with decelerating receivers for ion beam reception. Sample calculations for design of such a receiver for the isotopes of lithium are presented. Estimates of maximum production and requirements to attain such production are given. The maximum ion beam envisioned is 17 amperes obtained from extrapolation of experimental results."

From introduction: "The work described in this report was carried out as part of the feasibility study (ORNL-117) of a supercritical water reactor (SCWR) for use in nuclear propulsion of aircraft. The object of this work was to study the dynamic behavior of a particular design of supercritical water reactor. Numerical results are presented in Appendix I."

From summary: "Construction of the HRE facility was essentially complete on November 15, 1951 except for minor revisions and final testing. A program of engineering and nuclear tests of the system hasbeen drawn up, and the tests will be started early in the next quarter. The only major HRE items for which design is not complete are the samplers for the fuel, [gas], and reflector systems. These will be completed in time to be installed before critical experiments begin; meanwhile, temporary sampling devices have been installed for use during the testing program."

Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.

From introduction: "The purpose of the report is to set forth the development philosophy, objectives and expected results of the AEC-GE Nuclear Superheat Project."

From introduction: "This is the third of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."

From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker."

Study of the effects on Zircaloy-2 radiation corrosion of a high concentration of excess H2SO4 in a uranyl sulfate test solution using an in-pile loop experiment.