From introduction: "This report summarizes the work done on a study of fused-salt systems in a search for new liquid fuels suitable for use in a nuclear power reactor."

Abstract: "The solubility of the solid, UO2C2O4 x rH2O, was measured at various acid and uranyl nitrate concentrations. The results of the measurements prove the existence of the uranyl oxalate complex - UO2C2O4, in solutions containing excess UO2^2."

This is a progress report compiled by the chemical development department of the Carbide and Carbon Chemicals Corporation's Y-12 plant, discussing work on the carbonate (Monticello) process, as well as the recovery of uranium and vanadium from carbonate liquors.

A preliminary study of positive pion production from proton-nucleus collisions revealed that positive pion production cross sections agree more favorably with a Z 2/3 variation than with a variation proportional to the atomic number. A similar study on negative pion production has shown that negative pion yields from proton-nucleus collisions tend to vary in proportion to the number of neutrons in the nucleus. As a result an experiment was performed to investigate if there is a significant change in positive pion production with changing atomic number at two lower pion energies.

Abstract: This technical report describes the as-constructed SM-1 penetrated gasket designed for SM-1 Core and Flow Instrumentation (Task XIV). This report supplements APAE No. 79, The Summary Hazards Report for Task XIV, and evaluates the effects of a postulated failure of this gasket. The effects of failure on the Maximum Credible Accident are determined and conclusions and recommendations for the use of this gasket are made.

Abstract: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during a loss of flow accident, ART-02, a one-dimensional code, was used. This analysis indicates the SM-2 core is safe from burnout under steady state operation at design power level (28 tMW) because (1) no nucleate boiling exists, and (2) the minimum burnout ratio is above 2.0. The core is safe from burnout under loss of flow transient because the minimum burnout ratio in the hottest element channel of 1. 82 is above the minimum design criteria of 1. 5.

This work was performed to develop a general chemical method for the determination of small amounts of plutonium in solution. The work showed that a coulometric titration based on the preliminary oxidation of the plutonium to Pu (VI) followed by titration with electrolytically-generated ferrous ion to Pu (IV) was such a general method and was subject to few interferences. The significance of the work is that a chemical determination of plutonium can be made for amounts of plutonium heretofore determined only by radioassay methods, and the chemical determination of larger amounts are made more readily and with higher precision than with previous methods. The work also extends the application of coulometric titration methods to a new substance.

Uranium extractions from carbonate solutions were effective and phase separation rates were rapid using a new commercial quaternary extractant, Alamine 336. Extraction coefficients were approximately proportional to the quaternary concentration. Addition of -0.5 mole tridecanol/mole quaternary to the solvent gave optimum extraction efficiency and phase separation rates.