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.

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 describes a successful procedure used for the determination of americium in the presence of plutonium. Provided are articles listed that describe the research done in developing the method.

"An apparatus was designed and fabricated to obtain film samples from irradiated process slugs. This apparatus has been used to obtain film samples from slugs of the sodium dichromate elimination test."

Report discussing a study on the number of radioactive particles in the atmosphere by Hanford Works. The study's l procedures and results are included.

From introduction: "Analytical procedures for the determination of plutonium samples from the extraction and concentration plants utilize the carrying of the hydroxylamine-reduced trivulent plutonium by coprecipitation on lanthanum fluoride. Most other plutonium procedures also take advantage of the efficient carrying on lanthanum fluoride."

The following report describes the process to determine the method for determination of americium in the presence of plutonium and uranium.

This report presents data recorded during a program made to improve uranium slug quality in January, 1952, to determine what improvements could be made in the welding process.

Report evaluating different methods of preparing nitric acid solution and different methods of separating plutonium from this nitric acid solution of slag and crucible. Methods are explained and experimental data is given.

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.

Report discussing a study of various types of mercuric salts in order to determine which salt prevents the evolution of iodine which results from sparging.

From introduction: "The prime motive behind the experiments described in this report and in those preceding it in this series is the desire to reduce the number of Redox cycles necessary for decontamination from fission products of the plutonium and uranium streams sufficient to allow final disposition of these two products...This report deals with the mechanics of manganese dioxide handing, laboratory development of manganese dioxide scavenging, and a series of experiments at multicurie level combining ruthenium volatilization and manganese dioxide scavenging in stainless steel equipment."

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."

This report follows an investigation on how hydrolysis products of tributyl phosphate (such as dibutyl and monobutyl phosphoric acids, orthophosphoric acid and butanol) effect the tributyl phosphate process for uranium recovery.

A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.

The following report follows a test for remelting and casting uranium scrap specified that a pressure of 25 microns or less must be attained within the furnace before a charge is melted. The report was made to evaluate the effect of furnace pressures upon the quality if recast uranium metal.

The following document analyzes plutonium in urine which uses nuclear track film for evaluation of the quantity of separated plutonium.

Several studies of power recovery from Hanford pile effluents have been made, from which the conclusion can be drawn that, while recovery of power is feasible, it is costly because of the large volume of vapor which must be handled per kilowatt-hour of energy provided. This note is to call attention to the possibility of developing cheaper machinery than the conventional low-pressure turbine stages considered in previous studies through use of a water expansion cycle.

The determination of various parameters such as thermal utilization, resonance escape probability, control rod calibrations and etc. is often accomplished by the measurement of the pile period due to some given perturbation. With the present thoughts being directed towards plutonium fueled reactors, it was felt worthwhile to discuss a few of the basic differences in pile neutron behavior due to the smaller fraction of delayed neutrons per fission of Pu239 and the larger fraction of delayed neutrons per fast fission of U238 than occurs from fission of U235 alone.

As recommended in a previous report a study of the NO₂ and HNO₃ exposures of plant personnel in the 224 U Building has been made. Concentrations of NO₂ and HNO₃ from the 224 U roof stack, in the concentrator cells, and in the calcining pot rooms have been determined. The problems have been outlined and recommendations have been made for its alleviation.

For many years effort has been directed toward the development of means for the practical utilization of the heat evolved from the radioactive decay of certain fission and irradiation products. Fission products, in view of their availability in the plentiful, high-level wastes resulting from the processing of irradiated, nuclear reactor fuels have been most intensively studied for applications where their heat of decay might be converted into useful energy such as electricity for the operations of certain devices in place of chemical batteries . In addition other materials having desired radioactive properties may be produced by neutron bombardment of readily available elements.

The study of the flame photometric method for determining the concentration of tributylphosphate (TBP) in a hydrocarbon diluent was undertaken because it showed promise of being economically competitive and subject to fewer interferences than the existing methods. The determination of TBP in the hydrocarbon solutions throughout the range 0.01 to 80 per cent TBP may be performed using the flame photometer. The principal conclusions resulting from the study found a that there was higher precision in the one to two percent TBP rang than the 45 per cent TBP level due to error in reproducing narrow slit width in the higher range, 2) nitric acid, uranyl nitrate, and thorium nitrate all interfere if present but can be eliminated by contacting the solution with water or sodium carbonate solution. 3) a single determination may be made in 15 minutes, multiple determinations can be made at a rate of one to two minutes per determination, and 4) a modification of an existing method makes possible the application of this method to the determination of TBP dissolved in aqueous samples. A relative precision of plus of minus five per cent (95 per cent confidence level) is obtained.

A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.