Summary: A method was found for determining calcium concentrations in TBP process streams in spite of serious interferences bysodium, ferrous, uranyl, sulfate, phosphate, and sulfamate ions as well as by TBP. The precision attainable varied from sample to sample, depending upon its composition. In general, errors of 20% or greater occurred. The smallest determinable amount of calcium was about 10 mg/1.

The angular distribution of charged pions from 100 = 30 Mev neutron bombardment of C12 and Be9 has been measured. These data may be used to infer, by subtraction, the identity, within limits, of the [formula] and [formula] angular distributions.

Field tests were conducted to measure short-period pollutant concentrations at several stack heights during conditions of marked atmospheric instability and low wind speeds. The source was a mechanical smoke generator located at the 185-ft level of a tower.

This report describes the specifications, materials and the sequence of operations used to found and fabricate the first charge of enriched uranium fuel in the Experimental Breeder Reactor.

A series of measurements of ε in slightly enriched uranium, light water lattices is presently under way at Brookhaven. Figure 1 shows ε as a function of water-to-metal ratio for .600" diameter rods, of 1.3% enrichment. Because of interaction between neighboring groups of rods, ε increases rapidly as the water-to-metal ratio decreases.

Abstract: "The age-diffusion is adequate to describe the neutron behavior of a very large class of nonthermal reactors (all except those whose dimensions are comparable to the neutron mean free path). Thus, a convenient means of obtaining an accurate solution to this equation is very useful for general reactor calculations. Methods for reducing the age-diffusion equation to a finite set of coupled ordinary differential equations, called multigroup equations, are described. The relative merits of several alternate schemes are discussed. The multigroup equations may be solved by iterative procedures based on an assumed spatial distribution of the fission source neutrons. In practice the initially assumed source shape is accurate enough so that additional iterations are unnecessary. Analytical and numerical methods for solving the multigroup equations with the assumed source are discussed. The adjoint equations are also reduced to multigroup form, and examples of the adjoint function in obtaining improved reactivity values are given."

This report presents the final results from the investigation of the ratio of Pu-239 fission cross section to U-235 fission cross section. Three sets of plutonium and uranium foils were prepared at KAPL and were investigated to acquire the final results.

This report describes progress in testing nonaqueous extractive methods for leaching Western ores of uranium and vanadium

This report describes the progress on the experimental breeder reactor. It focuses on the approach to critical experiments, calibration of controls and flues and flux distributions.

Abstract: "UO2 and ThO2 form a continuous series of solid solutions with the solidus-liquidus from 2875 C for UO2 to above 3200 C for ThO2."