Report discussing a method for the stepwise calculation of the number of transfer units utilized in a given solvent extraction operation. "Use of the method results in a very appreciable saving in time of calculation with an error of 1.5% for the runs tested. The error tends to become smaller with increasing total numbers of transfer units involved."

Technical report outlining a method for the electrodeposition of adherent deposits of both aluminum and zirconium on uranium. Report finds that current efficiencies are good for aluminum deposition but low for the zirconium baths. [From Abstract]

Technical report describing the tests on types 309, 316, and 347 stainless steel. These steels were tested for a total of 779 to 828 hours in three different synthetic waste solutions. Results shoe that the best all-around corrosion resistance to the test conditions was exhibited by 316 stainless steel, but in one solution 347 stainless steel was more resistant. [From Abstract]

Technical report outlining the use of the Carbagel process in nuclear reactors, its technical feasibility, and case studies of the Carbagel process and its theoretical and technical use for reactors such as the Brookhaven National Laboratory reactor.

From introduction: "The tube arrangement covered in this report was proposed in June, 1950, as a means of halving the weight and volume required for the heat exchanger. Ideally, the pressure drop across this arrangement should be little more than that required to overcome the skin friction on the tube surfaces. If the pressure drop across the tube spacers and in the cross-flow regions can be kept low, this ideal can be approached. much of the test work covered in this report was devoted to this phase of the problem."

Technical report detailing kinetic equations that have been developed for a boiling-type reactor and inherent reactor stability studies that have been made on the basis of these equations. Presents features of the proposed reactor, comparisons of circulating types, investigations of bubble-rise velocities, effects of transient conditions of vapor mass in steam chest, and bubble time delay functions yield favorable results. [From Abstract]

Report discussing equipment that can be used to perform chemical and mechanical operations involving radioactive materials safely. Illustrations of the equipment are provided.

Abstract: "The definitions of the fundamental measures of calutron operation including enhancement, current ratio, and process efficiency are set forth with derivations of the relationships between them. An analysis of the plant process is carried out for both the tanks limited and the charge limited case. Equations are derived for plant X output and plant X utilization efficiency. Effective production is defined and the value of increment to a mass of product material in terms of effective production is determined. An equation giving the X concentration below which product material should be reprocessed is derived."

Data on the crystal structures of the common modifications of the elements at zero pressure.

This technical report is intended as a brief description of the free convection problem existing in the various annuli of the SIR Mark A rotating plugs. It is by no means a complete report of the plug "hot tests", but merely records some of the more significant experimental observations and presents a few of the theories and calculations made to explain the observed free convection phenomenon. The general discussion which follows is chronological. Details of analyses are relegated to the Appendix.

"Absorption measurements have been made in a large body of water to evaluate the contribution to the radiation intensity produced by the degradation of radiation without absorption. Radiation intensities three times those expected from a simple exponential absorption were found. Scattering from the air of gamma radiation has been measured and has been found to agree satisfactorily with theoretical predictions. The penetration of radiation through curved pipes in shielding has been measured and been found to be a flat topped function. A 2" pipe bent in the arc of a circle of 7' chord and a 10' radius gives a reduction intensity over the intensity in air at the same distance of 2.5X10⁴."

This document describes a method in determining solid solubilities using strain-aging techniques, explaining a non-uniform yielding of the alloy in question.

Abstract: "The spectrum of plutonium has been observed over the temperature range of 2000 to 2600 C and a wavelength coverage of 3476 to 6888 A. The spectrum was excited in a modified King furnace."

Report discussing the design, construction, and testing of a pilot plant for the fluidization of uranium trioxide to create uranium tetrachloride. The plant yielded 97.0% "immediately available as product."

Report discussing tests that were carried out to determine if a few parts per million of boron can be removed directly from beryllium oxide powder without chemically changing the BeO during the process.

Abstract: "A gravimetric procedure is described for the analysis of indium-plutonium solutions. This procedure consists of a preliminary separation of the plutonium as the peroxide, followed by the quantitative precipitation of indium diethyl dithio carbamate from a slightly acid solution. The precipitate is dried at 105 C and weighed. Recoveries of 99.4 - 100.5% with an average precision of 2.3/100 were obtained on known Pu-In solutions containing 5 - 50 mg of indium per sample."

The following report describes the design and construction of the reactor building wing, designed to attach to the reactor building for the Argonne National Laboratory.

Report discussing assaying techniques used in the Department of Metallurgy at the Massachusetts Institute of Technology, as well as the equipment used for the techniques.

This report discusses the process of zirconium purification, providing an alternate method for converting ZrCl4 solution to the oxide in order to free it from small amounts of hafnium impurity that are naturally present.

The following report was written to replace previous directions submitted in the February 6, 1943 report on the preparation of the solution X(OC₂H₅)₅.

Due to some lack of knowledge of the energy per fission, there has been some uncertainty over the absolute power of the Bulk Shielding Reactor. This report analyzes measurements to state the absolute power of the BSR within a few percent.

The following report describes the use of two experimental facilities used to evaluate the Schenectady Pile. The facilities are divided into nuclear physics and chemistry experiments, and testing of pile components and materials under pile conditions. This document discusses the experiments taken place in these facilities to evaluate the pile.

Abstract: "Methods for recovering radium from K-65 residue have been investigated. A process using Versene was developed and demonstrated on a laboratory scale. In this process K-65 residue is leached with Versene solution and radium is adsorbed from the leach liquors and purified by the use of cation exchange resin."

Introduction: "This report is an extension of NAA-SR-Memo-178. The results show the number of control rods as a function of the amount of reactivity to be controlled. Numerical solutions are given for a typical example and are readily obtainable for other cases."