In the canning operation, the preparation of aluminum components is important in assuring uniform wetting of the aluminum surfaces with Al-Si. The surfaces of the components should be free of dirt and grease and should also have a minimum retention of non-metallic film, normally aluminum oxide, for the best wetting properties. At present, dirt and grease are removed satisfactorily by a vapor degreaser followed by a Duponol-alkaline wash. The standard specified method of removing the aluminum oxide film from aluminum cans is a four-minute etch in twenty percent phosphoric acid. The oxide is removed from the caps by an eight-minute etch in twenty per cent phosphoric acid or an alternate etch of a one percent solution of hydrofluosilicic acid. If the phosphoric acid etch is not controlled properly, it is possible to form a thin, inert phosphate coating on the surface of the aluminum, which is undesirable for good wetting characteristics. In an effort to find a better etchant for aluminum components, an investigation of various commercial and non-commercial etchants was undertaken. This report details results of this investigation.

Since Redox start-up, several samples of Redox PR solution have been evaporated in the laboratory as one step in a study of the Redox -- 234 coupling process. Because feed for Task I in 234-5 will be produced by evaporative concentration of Redox and purex product solutions, and because laboratory work has shown the desirability of filtering Redox solutions after such evaporation prior to use in Task I. This report summarizes the observations which have been made in the course of this work, as a guide in the design of filters for the Redox and/or Purex PR cages.

This document provides a bibliography of reports concerning Hanford type fuel rod central temperatures. The documents are listed chronologically, the most recent first.

Increases in process water flows will be needed as the current program of increasing pile power levels continues. The future process water flows that will be required are known to be beyond the present maximum capacities of component parts of the water system. It is desirable to determine the present maximum capacities of each major component part so that plans can be mode for modifications and/or additions to the present equipment to meet future required flows. The apparent hydraulic limit of the present piles is about 68,000 gpm. This figure is based on a tube inlet pressure of 400 psi, a tube flow of 34 gpm, and 2,000 effective tubes. In this document the results of tests and calculations to determine the present maximum capacities of each major component part of the 100-B water system will be presented. Emergency steam operated pumps will not be considered as it is doubtful of year around operation of a steam driven pump could be economically justified. Some possible ways to increase the process water flows of each component part of the water system to the ultimate of 68,000 gpm are given.

Laboratory experience on the precipitation of Pu(IV) oxalate is summarized. Filterable Pu(IV) oxalate with a cake density of 0.6 to 0.7 g Pu/cm/sup 3/ cake was precipitated from Redox PR solutions containing 10 to 200 g/l Pu and 2 to 6 M HNO/sub 3/. Filtration ease increased with strike temperature from 35 to 60/sup 0/C. Optimum conditions for pre-reduction of Pu(VI) to (IV), precipitation, digestion, filtration and washing were determined for 60 g/l Pu. Separation factors of 80, 40, 20, and 12 for Al, Cr, Fe, and U and decontamination factors of 1.2, 12, and 3 for Am, Ru, and Zr--Nb were obtained.

This is a progress report of the production reactors on the Hanford Reservation for the month of March 1953. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

The objective of this study is to provide a simple method for calculating exposures for the various laboratory procedures which involve penetrating radiations. With this method it will be possible to evaluate and record on a day to day basis the total exposure received during laboratory work. It will also provide reliable information for exposure investigations.

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This report addresses an experimental program that was undertaken to investigate means of safely and conveniently disposing of certain halogen-bearing materials from an air stream.

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Some time ago, a series of experiments (the P-11 project) were conducted to determine the critical mass of plutonium in variously sized and shaped vessels and with various solution concentrations. These experiments were rather general in nature, hence, it is necessary to interpret the data to the specific critical mass problems of interest in separation processes. The design of new continuous flow separation processes calls for even further extrapolations of these data to vessel geometries far from the range of present experimental knowledge. The purpose of this report is to review for reference the estimates used in the design of the critically safe portions of Purex and Recuplex. This report is compiled for engineering use in approximate design; however, any design of vessels involving criticality hazards will be reviewed by the Critical Mass Group.

A study was made of the effect of the addition of V aad Si on the properties of Th; corrosion of stainless steel in uranyl sulfate; corrosion, brazing, and welding of stainless steel; properties of Ti; method of combining deuterium and O for return to the reactor; spot welding of fuel elements; fabrication of reactor fuel elements; mechanical testing of U, Th, and stainless steel; surface rearrangements on a single crystal of Cu in contact with a saturated solution of Cu in Bi; development of cermets for reactor components; fabrication of Th-U fuel elements and Al-U alloy componerts. (J.E.D.)

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This report details activities of the Chemistry Unit at the Hanford Atomic Products Operation for the months of January, February, and March of 1953.

The continuous plutonium concentration facilities proposed for the Purex Plant consist of a stripper-concentration unit in which the organic is removed and a portion of the required evaporation is accomplished, plutonium concentrator (No. 1 Pu Conc.) in which the final plutonium concentrate is produced, and a second concentrator which re-evaporates the totally condensed overhead from the No. 1 Pu Concentrator. In this report the Purex concentration ``package`` has been examined to determine whether the design is suitable for concentrating the various Redox 3BP solutions which may be produced (variable nitric acid to plutonium ratios) during operation at Redox Phase II processing rates. In Appendix {Lambda} a short-cut method is presented for the calculation of the operating conditions to be employed around the No. 1 and No. 2 Pu concentrators to produce a desired Pu-HNO{sub 3} product stream from a given feed solution. This method is considerably simpler than the trail-and-error solutions generally employed for such problems.

The usefulness of the Ewing equation for calculating the thermal conductivity of reactor metals and alloys from electrical resistance, specific heat, density, and atomic weight was investigated. The alloys investigated were Zircaloy-2, HSZA, Nb- 5.5 wt% V, Inconel, 18-8 stainless steel, and eutectic NaK. The Ewing equation was found to give calculated values with a degree of confidence similar to that of actual measured values. (auth)

A set of four strong focusing magnetic quadrupole lenses has been constructed and operated. Each lens consists of four air cooled electromagnets with pole tips having a hyperbolic cross section. Each lens is 4 in. long and has an aperture 2 in. in diameter. Measurements of the magnetic field demonstrate that the hyperbolic cross section satisfies the requirements of a constant magnetic field gradient very well. The technique of deflecting a current carrying flexible wire has been used to measure the trajectory of charged particles through the system of lenses. It has been observed that the strong focusing requirements are satisfied. The system of lenses was then used to focus 0.5 Mev protons, 20 Mev deuterons, and 40 Mev alpha particles. The parallel beam of 0.5 Mev protons was detected by observing the incandescence of a quartz plate while the protons were bombarding it. The focused beam was less than 1 mm in diameter. The astigmatic 20 Mev deuteron beam from the 60 in. cyclotron was increased in current density by a factor greater than 30.

This document from Savannah River Plant reports monthly progress on the following topics: heavy water corrosion, reactor materials, reactor technology, separations technology, and instrument development.