Report discussing the properties of plutonium and plutonium's distribution between hexone and aqueous phases, which relates to the function of Redox plants

The following report describes a countercurrent extraction column, which employs timed solenoid valves and pressurized feeds to provide a pulsing action to disperse the phases. This report further describes the 4-stage cycle of the column operation.

Purpose: "This test was conducted to gain information and experience in the handling of heavy aggregate concrete. The results from this test were to establish procedures for a subsequent program -- "Construction Test of High Density Concrete Shielding.""

The following report is one of a series of rolling tests to establish the rolling process for Feed Materials Production Center at Fernold, Ohio. The primary objective of this program is to find a mechanically feasible process for continuous rolling of uranium.

Report summarizing corrosion tests meant to determine the corrosion rates of bronze, mild steel, T-304 stainless steel and 2S aluminum in 10% potassium tetraborate solution. Tests were completed under the boiling point of each solution except for 2S aluminum, which was tested at 40C, the approximate temperature in a pile.

The following report provides data from corrosion tests meant to evaluate the performance of Type 3098Cb stainless steel in BiP04 process dissolver solution containing mercuric ion.

"The attached report summarizes the work performed in the establishment of an improved spectrographic method for determining iron in plutonium."

Introduction: "Knowledge of the mechanical properties of uranium at elevated temperature is essential in order to understand and predict the fabrication characteristics and pile behavior of this metal. This report presents the experimental data obtained from beta heat-treated specimens which were originally machined from one production, alpha-rolled uranium rod."

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 discusses the calcination or heating of UO₃. When UO₃ is heated, it loses ionic impurities and can produce uranyl peroxide.

Thermal spikes occurring during the life of a slug in a pile cause a momentary destruction of the original configuration of atoms in the metal. This process occurs at such a rate that in a thermal neutron flux of 10(13) neutrons per square centimeter per second each atom in the metal will be subject to temperatures above the melting point of uranium every 40 minutes.

The following report deals with the application of the water boiler neutron source to the exponential experiments in an attempt to speed up lattice testing measurements.

This following report discusses certain topics pertinent to the x-ray photometric method, such as the optimum size of sample and of sample concentration, the technique of measurement for high precision, the use of easily prepared uranium standards for future calibrations and corrections for extraneous substances, and it compares results obtained by both x-ray and chemical assays.

This report follows a manuscript report made in January 11, 1952, and provides results of a survey that gives corrections as well as suggestions for new and local sources of aggregate material in comparison to the original report. These reports were made in response to a heavy desire of improvement in reactor design and shielding.

Foils of plutonium 239 and uranium 235 have been mounted back to back in a dual ionization fission chamber in the diffracted beam of the Hanford neutron crystal spectrometer. A quantity proportional to the ration of fission cross sections of Pu239 to U235 has been measured as a function of neutron energy from 0.020 to 1.0 electron volts. The results of this investigation are presented graphically in the text.

Thirty gram patches of plutonium dioxide can be readily chlorinated by reaction with phosgene or carbon tetrachloride at temperatures of 350 and 450 C respectively. Plutonium trichloride prepared by either method can be reduced to the metal in a hermetically sealed bomb by reaction with calcium. On a twenty gram scale yields of approximately 97 per cent are obtained when a calcium-iodine booster is employed. It has been demonstrated that a method for reduction of plutonium trichloride to the metal without the use of a booster can be development.

Supervision and coordination of shutdown work are often made difficult by lack of visual contact between the front face, rear face and control room. Examples of such conditions are: Removal of process tubes, where close co-separation between front and rear elevator crews is required; Locating freshly discharged slugs accidently lodged on discharge face obstructions where radiation levels are high and optical viewing equipment inadequate; Monitoring of the transfer of hot samples from a process tube into a cask, where permissible exposure time is short and oral briefing of personnel who must perform subsequent operations is inadequate.

The automatic polarograph is ideally suited for the analysis of waste streams for uranium in the Metal Recovery Process, and with modification, it is applicable to other processes, pilot plants, and even to laboratory set ups. The instrument is simple, dependable, and relatively trouble free in operation. It provides an immediate record of the uranium in the waste and, through better control of the process, lower processing costs.

Various non-linear calculations for heat conduction in an istropic, homogeneous medium are presented.

Unanticipated radioactive contamination of the 200 Areas environs was discovered in the latter part of 1947, about 2.5 years after the startup of the Bismuth Phosphate Separation Plants. It was subsequently established that this contamination was due to radioactive particles emanating from the Separation Plants' stacks, and the need for exhaust ventilation air filtration equipment was recognized. Sand filters were installed in the fall of 1948 in the ventilation systems of the B and T Bismuth Phosphate Plants. These filter units essentially eliminated this contamination problem and have performed satisfactorily to the present time.

Many procedures for the chemical isolation of the microscopic angular inclusions in rolled uranium have been investigated. Four were selected as most satisfactory for this work and will be described in detail. The procedures are: (1) the copper displacement of the uranium, (2) the electrolytic displacement of the uranium, (3) the chemical dissolution of the uranium in an anhydrous solution of hydrogen chloride in methanol, and (4) the chemical dissolution of the uranium in an aqueous solution of hydrogen chloride and hydrogen peroxide.

Laboratory studies have shown that the double salt, CaF2-PuF4, can be precipitated by rapid addition of hydro-fluoric acid to solutions containing 25 to 75 g Pu/1, caleium equimolar to plutonium, and 1 to 10 M HNO3. The precipitate, which is subsequently washed with water and dried to 300 degrees C in dehumidified, deoxygenated argon, can be reduced thermally by calcium to give high yields of plutonium metal.

In view of the increasing number of methods for determining plutonium in terms of weight rather than radioactivity, a need has arisen for a plutonium compound that can be used as a gravimetric standard. An easily prepared compound that dissolves readily in nitric acid is desirable. The present study was made to determine the feasibility of using plutonium triflouride as a plutonium standard. The preparation, composition, stability, and ignition of the compound are discuss, as are certain properties of the plutonium dioxide resulting from ignition of the trifluoride.

The very strong flux gradient in the MTR reflector might be thought to be some cause of worry. However, this gradient will be minimized by the presence of the large block of aluminum, which, because of its small effect on neutrons, will tend to flatten the neutron flux in its vicinity. Advantage should be taken of the shape of the test facility by placing the water hole corner closest to the MTR core. This placement should take best advantage of the flattening potentialities of the slowing-down flux from the test slugs, by placing the nearest (beryllium) moderator on the low flux side of the assembly.