Introduction:"A corrosion test program in support of the Redox Project was carried out during the second quarter of 1950 to determine the corrosion rates of several austenitic stainless steels in simulated 202-B Waste Storage solution containing HF, HN03, and H2SO4 acids. The results of this program are contained herein and all original data are recorded in laboratory notebook HW-3282-T."

Abstract: An analysis of the lid tank neutron data for Pb-H2O and Fe-H2O is made. "Effective" fast neutron cross sections for the metals are obtained. This is based on the "one collision theory" of shielding. Values are 3.4 barns for Pb and 2.0 barns for Fe. These compare very well with those obtained by Albert and Welton based on other lid tank data and another method of calculation.

As a result of unreported information, it was suspected by some people that a change in dimension was experienced by 2S Aluminum due to a sudden change in neutron flux impinging on it. This was thought to be of the order of 500 microinches per inch in magnitude. Such an effect, if present, could help explain some of the creep phenomena reported lately (i.e. change in creep rate due to cyclotron bombardment.)

It is the purpose of this report to present a quantitative picture of the overall waste problems at the presently operating major A.E.C. sites. Presented herewith are data on the volumes and radioactive concentrations of the wastes handled and effluents discharged, available tankage and processes flow sheets from each site.

This report helps determine tritium in the range of 0.1 to 100% in other gases using an ion chamber that is analyzed within this report.

Secondary charge effects from a 10 kilovolt proton beam and their effect upon beam current measurement are investigated. A collector is designed for beam current metering of a 60 kilovolt proton beam by means of charge measurement and energy measurement.

Report discussing thermodynamic measurements and calculations made regarding couples of neptunium ions in perchloric acid.

The following report discusses an equation derived by which the maximum allowable concentration in the atmosphere of a beta-omitting isotope for which lung damage is the limiting consideration can be calculated.

Abstract: "A small low impedance flux monitoring device has been built which utilizes the heating (and consequent chance in resistance) of a boron coated platinum wire. Feasibility tests in the Argonne-GP-3 reactor indicate that it may develop into a wide range instrument, particularly useful at high flux levels. Design and constructional details of the bolometer and its associated circuits are given. The circuitry is somewhat unique since it is in effect an all electronic self-balancing bridge. Future lines of research are suggested to solve some of the remaining problems."

Leaching investigations on low grade Belgian Congo uranium ores and recovery of uranium from acid leach solutions by uranous phosphate precipitation, uranyl phosphate precipitation and by sodium carbonate retreatment of alkali precipitates are described.

As there is no accurate measurements of the energy distribution of neutrons emerging from large uranium blocks, it becomes of importance to see how much information of this kind can be derived from the slowing down distribution of the neutrons in a water tank.

From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."

This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.

A method for determining zirconium in plutonium-zirconium alloys was required as part of an investigation of alloys containing fissionable material, with possible use in nuclear reactors. Alloys of these two elements were brought into solution with a bisulfate fusion and the zirconium was separated by precipitation with p-bromomandelic acid. Determinations were completed by weighing the zirconium oxide obtained after ignition of the precipitate at 925 degree C. The precision of this recommended procedure was estimated in terms of the standard deviation for quadruplicate determinations, made with weight aliquots from dissolved alloy samples. The range for the standard deviation was 0.5 to 1.7 parts per thousand for samples from which aliquots each containing 9 to 15 mg of zirconium were selected. The complete recovery of zirconium from solutions of pure zirconyl chloride and plutonium trichloride was shown by the 95 percent confidence limits of 99.9 +- 0.3 percent for the average of four determinations, observed with samples containing 5 to12 mg of zirconium in the presence of 10 to 20 mg of plutonium. It was found the Mo, La, PU(III), and K2Cr2O7 do not interfere with zirconium determinations made according to the recommended procedures, but Pu(IV) does interfere slightly. It was …

Summary of the research progress meeting of June 12, 1952

Abstract: "A uranium-titanium constitution diagram is presented. There is complete solid solubility between titanium and gamma uranium above about 2100 F. Only one compound exists in the system. It has a hexagonal structure based on U2Ti. It has a fairly wide range of stability, particularly on the titanium side. Beta-titanium solid solution decomposes eutectoidally into alpha titanium and compound at 1150 F. Eutectoid composition is about 72 atomic per cent titanium. Gamma-uranium solid solution decomposes eutectoidally at 1325 F into beta uranium and compound. Eutectoid composition is about 6 atomic per cent titanium. Beta uranium and compound react peritectoidally at 1233 F to give alpha uranium. Solubility of titanium in alpha and beta uranium is low as is the solubility or uranium in alpha titanium."

Abstract: "Experiments were performed to characterize the types of nitro compounds that might be formed by reaction of Shell Spray Base with nitric acid, to determine the extent of their formation, if any, and their path under conditions of nitric acid recovery in the Purex Process. It is concluded that the instability of Shell Spray Base to nitration, under conditions to prevail in the plant, presents neither a disposal problem nor a safety problem."

This report examines a uranium slug that has been produced by powder metallurgical methods and exposed in the 100-DR Pile and was deformed during pile exposure.

The following report analyzes random walks and whether or not they can be used to shed any light on problems of neutron diffusion.

The object of the work performed under this contract was to investigate the possibility of gas plating copper base metal with (a) pure chromium metal from chromium hexacarbonyl vapor; (b) chromium-nickel plating from a mixture of chromium hexacarbonyl and nickel tetracarbonyl. The object of the work performed during the final month was to confirm the fact that the gas plating of chromium metal and chromium-nickel laminates free from nitrides, oxides and carbides was practical.

"Neutron total cross sections for bismuth and uranium have been measured in a good geometry transmission experiment, using a time-of-flight instrumentation. The source of neutrons was the stripped deuteron beam of the 184-inch synchrocyclotron. The results are shown in Fig. 1. Uncertainties are shown in terms of standard deviations, due to counting statistics only, and to energy channel width."

Recent studies on the separation of cobalt and nickel and on the behavior of iron in hydrochloric acid on Dowex-1 resin in relation to the selective adsorption of chloride complexes of these elements have suggested the use of resin for the separation of iron and cobalt.

Introduction: "Because of the importance of the value of the transport mean free path of thermal neutrons in deuterium oxide, Kash and Woods proposed to redetermine this value in deuterium oxide (99.4 atom-percent deuterium, by an extrapolation method. Kash and Woods thought that the low value of the transport mean free path might be a source of error. This paper relates studies of procedures by which (1) boron material would be dissolved in high content deuterium oxide without adding foreign atoms, particularly hydrogen atoms which might adversely affect the test, (2) the boron content of the deuterium oxide solvent may be determined, (3) ion exchangers may be deuterized and de-deuterized, and (4) ion exchange may remove specific ions from solution."

Abstract: "The cross section for this reaction is calculated for three Hulthen deuteron wave functions. A hard core in the deuteron at one-half meson Compton wavelength reduces the total cross section and flattens the angular distribution in the backwards direction in agreement with experiment."