"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."

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.

Six structural materials (aluminum 2S, aluminum 72S, copper, iron, steel, lead and bismuth) were irradiated for about 100 kilowatt hours in the center of the Argonne pile. The alpha and gamma decays were then followed for 130 days on Geiger counters and are presented here graphically as number of rays per minute per gram per kilowatt hour vs. time of decay. A quantitative interpretation of the gamma-ray decay curves gave fair agreement with the chemical analysis of impurities found in the materials.

Abstract. to estimate the oxygen picked up by thorium in casting a rapid method of running the acid insoluble content was developed. the quickest procedure consists of reacting with mixed acids, fuming with perchloric and filtration to separate the "free" thorium from the "combined". The precipitate is ignited and weighed as thorium dioxide.

"This report is concerned with the effectiveness of this washback procedure in reducing the phosphate concentration and also with other methods by which the simultaneous extraction of phosphate along with tuballoy may be minimized."

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."

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."

From introduction: "The analysis of mixtures of fission products with a mass spectrograph offers certain advantages. A chemical separation of the fission products found in the solution at Hanford is not necessary with the mass spectrograph technique. A sample of the mixtures can be placed on the sample holder and then the sample holder is mounted in the mass spectrograph. This reduces the amount of handling of the active solutions to one relatively simple and short operation. The health hazards involved in the analysis can be further reduced by increasing the efficiency of the spectrograph as much as possible, thus making possible an analysis of a sample of lower total activity. The mass spectrograph described here is an attempt to realize the advantages pointed out above. Particular attention has been given to increasing the increasing the efficiency of the instrument."

The document consists of two photographs and ten drawing of an electrolysis assembly for electroplating radioactive samples and one drawing of a thin-window Beta-counter. Included are a cell support, an electrolysis cell, electrolysis cell cathode, cell rack, Geiger counter absorber slide, carrier for electrolysis cell cathodes, and a cover for electrolysis cell cathode carrier.

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.

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.

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.

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

The following report examines the fission counter, fission plates and activation results of the neutron energy distribution in the center of the Los Alamos plutonium reactor.

The following report provides data collected during an investigation in the Columbia River. The purpose of this investigation was to research the radioactivity present in the bottom-living organisms of the river.

Abstract: Magnetic susceptibilities per gram atomic weight of elements 92 to 95 in most of their oxidation states were measured at 20°C on 0.1 ml of solution which was 0.005 to 0.09M in heavy element. The values obtained (all paramagnetic) in units × 106 were: U(IV), 3690; Np(VI), 2060; Np(V), 4120; Np(IV), 4000; Pu(IV), 1610; Pu(III), 370; Am(III), 720. The results could be interpreted only on the basis of electronic configurations 5fn, even though susceptibilities were generally lower than the theoretical values and lower than experimental values for corresponding lanthanide 4fn cations. The lower values should be expected as a result of the Stark effect produced by electric fields of anions and of water dipoles. Failure of the Russell‐Saunders approximation to the coupling between electrons may account for some of the error in the theoretical calculations. That the susceptibilities of Pu(III) and Am(III) are manyfold lower than those of Sm(III) and Eu(III), respectively, is attributed to wider multiplet splitting in the actinide atoms.

Report discussing a study with the following objectives: "to synthesize pure specimens of both methylisoproplydiketone and 1,1 dinitroisobutane, to determine their physical and chemical properties, and to devise analytical methods which permit their quantitative determination in hexone-nitric acid systems to be encountered in the Redox Process."

This report is a document summarizing all information available on life aspects of various measures proposed to reduce or eliminate corrosion of Van Stone flanger.

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."

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.

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.

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.

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]

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."