The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.

Report describing a method for recovery of high yields of thorium and uranium from monazite sand concentrates. Monazite is decomposed into hydrous metal oxides, which are dissolved in an acid. The solution is then separated into a precipitate, which seperates from thorium and uranium. An alternate separation method is evaluated.

From abstract: "Details are presented on the processing of monazite sand and on separating the rare earths from thorium and uranium. Solvent-extraction and ion-exchange techniques for purifying thorium and uranium are described."

Abstract: "Costs have been estimated for the production of uranium and pure thorium from monasite concentrates by a process involving (1) reaction of monasite with caustic soda, (2) dissolution of the hydrous oxides in hydrochloric acid, (3) separation from the bulk of the rare earths by hydroxide precipitation of thorium and uranium, and (4) purification by solvent extraction."

Abstract: "The effects of acidity on extraction of vanadium and molybdenum by diethyl ether are described. Solubility data for several vanadium compounds in nitrate process solutions are presented. Preliminary results on the extraction of uranium from process slurries by tributyl phosphate are reported, including data on the contaminants extracted with the uranium."

From introduction: "This is the ninth monthly report, BMI-514, under Contract No. AT(30-1)-771 on "Zirconium Research and Development". The report covers the work period from September 15, 1950, to October 15, 1950. Work is continuing on the preparation of large-diameter zirconium crystal bars in the 16-inch-diameter de Boer unit. Crystal bars up to 1-5/16 inches in diameter and 8 feet long have been prepared in this unit."

Abstract: "The thermal and electrical conductivities of a series of Pu-Al alloys have been determined in the range 0.12 atomic percent Pu. The conductivities are approximately proportional to the volume of free aluminum."

The following report provides results from laboratory tests on the corrosion resistance of various types of stellite facings on astenitic stainless steel T-347 to Redox streams.

The following report observes infrared measurements in the region of OH bands, the C2O band vicinity, the low frequency end of the spectrum, and the region of the UO2 band on the system hexone - water - uranyl nitrate.

Report describing how the neutralized aqueous waste from the TBP Metal Recovery Process will be concentrated by evaporation to minimize the requirements for underground storage tank capacity.

Summary: "This investigation showed that a sound , weather-resistant coating can be applied to uranium that the surface to be plated is cleaned and etched properly. Using the proposed two-bath plating method at 80 C., a four-mil nickel coat can be deposited in thirteen hours."

Report discussing protactinium, including the element's history and the results of various experiments.

Report discussing research on the disposal of radioactive waste, specifically second-cycle waste and first-cycle neutralized waste. "In the absence of established environmental tolerances, the investigation reported herein have been directed for the most part in developing general methods of removing radioactivity from certain waste solutions to as low a value as practical."

Technical report outlining the theoretical study of the sub-critical BNL (Brookhaven National Laboratory) reactor, and a comparison of reactor performance with the purpose of presenting the experimental results of the experimental methods. Presents experimental results and and a detailed discussion of the experimental methods along with theoretical analysis and evaluation of the results.

Technical report about the liquidus curve for the nuclear reactors bismuth-uranium system and the need for a suitable container for this fuel.

Technical report outlining a preliminary design for carrying out the process of producing U233 from Th232.

Technical report discussing six problems in paramagnetic substances at low temperatures: 1) The Kramers degeneracy; 2) The quenching of orbital motion; 3) Curie constants of CuSO4∙5H2O; 4) Super exchange in CuSO4∙5H2O; 5) The specific heat of CuSO4∙5H2O; and 6) Nuclear interactions of paramagnetic ions. The discussion of these problems brings to light the general principles involved and the general principles can then help understanding of many low temperature phenomena in the paramagnetic salts.

Uranium can be rolled from cast metal or forged ingot to sheet satisfactory for cupping, deep drawing, and similar fabrication procedures by a combination of hot breakdown in the neighborhood of 600 deg C and warm finishing at 225 to 325 deg C. Sheet may also be obtained by hot rolling alone and by warm rolling alone. However, it is difficult to secure a uniform, controlled grain size by hot rolling only and warm rolling is time consuming because of the limited reduction per pass obtainable. The combination of hot and warm rolling afforded best and most practical method to secure good quality sheet in the quantity required. The percent reduction by hot working does not appear to be critical, but at least 60% warm reduction is desirable to obtain complete and controlled grain size by recrystallization with high ductility and strength properties. Except for research investigation, rolling of uranium below 225 deg C is not recommended. In the temperature range considered (below 225 deg C), reduction is difficult and must be limited to one to two percent if edge cracking is to be avoided. Hot rolling of unplated uranium from the as-cast or as-forged surface is recommended, using a …

This technical report presents results of nuclear plate work carried out to determine the neutron energy distribution inside the Los Alamos fast reactor. Most of the distributions which were investigated are valid over the energy region from 0.4 to 6 Mev. The results show that at the center of the reactor pot about 65% of the neutrons are located below 1 Mev in a rather narrow energy region which has a maximum in the neighborhood of 0.5 to 0.6 Mev. Above 2 Mev the energy distribution is similar to that of a plutonium fission neutron spectrum, i.e. the spectrum decreases exponentially, diminishing by a factor of 10 in intensity over an energy range of about 4 Mev. The leading geometry of the reactor pot does not seem to appreciably affect the spectrum at the center of the pot. However, spectra determined outside the pot can be significantly altered by the particular viewing geometry employed to examine the neutrons coming from the center of the reactor.