This document was prepared in response to a request from the Atomic Energy Commission for a brief review of the principal ideas and technical developments which might effect power levels over the following six years. Also requested were approximate data on any pile modifications that might be involved, including rough estimates covering possible cost and completion dates. A brief discussion of plans for increasing the power levels of the Hanford Piles is provided.

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During the history of operation of the Hanford reactors, several methods have been utilized to establish an outlet water temperature or ``Panellit`` limit based on the stability of water flowing through the process tubes. These methods have been known as ``Excess Header Pressure Limits,`` ``Trip Before Boiling Limits,`` and the most recent, ``Trip Before Instability Limits.`` Each new concept vas accepted only after considerable experimental data had proved the new method to be safe and operationally feasible. It is anticipated that in the future other tube outlet water temperature limits will be developed based on new technology. The purpose of this document is to present, in simple terms, an understandable explanation of previous operating limits, to discuss the status of the present Instability Limits, and to outline the direction of future work in raising the outlet water temperature limits.

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A summary of research progress is given in this report. (1) Half-dollar size corrosion samples of aluminum-clad uranium, which were pressed with 3, 4, 5, and 6 thousand psi, have begun to fail by undercutting between 7 and 21 days. This behavior is contradictory to that of previous samples similarly pressed with 6,000 psi; corrosion of these samples was restricted to pimples, which grew slowly in diameter and did not undercut. (2) Moczik Tool and Die Co. has designed a streamlined die and a mandrel tip for use with the extrusion cladding equipment at BMI. Other methods of extrusion cladding are still under consideration. (3) Experiments on the internal cladding of tubes are awaiting the completion of tools. (4) Casting of uranium-aluminum alloy billets has begun for the purpose of determining the affects of the rate of solidification on segregation in the alloy. (5) An accurate determination of the uranium-aluminum constitution diagram in the range 16 w/o to 40% has been inconclusive to date. (6) Nickel-tin alloy plated over a flash coat of nickel did not provided to satisfactory bonding material on samples of uranium press-clad with aluminum at 950 C, 6,000 psi for 5 minutes.

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This report consists of Chapter Six of the Nuclear Metallurgy Lectures. Chapter six discusses the reduction of uranium, chemical composition of uranium ores, extraction process for uranium ores, bomb reduction, green salt, and dingots.

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This report summarizes the effect of irradiation on the properties of fissionable and non-fissionable materials. General property changes, irradiation of zirconium, zirconium-tin alloys, the irradiation of aluminium, irradiation of thorium and uranium, are a few of the topics discussed.

A continuous belt drier capable of handling 1000 lbs of oxycarbonate per day was completed, installed, and operated to produce a satisfactory product for chlorination. An experimental chlorinator was also completed. All necessary pants were completed for the fabrication of Horizons' Mark VI continuous electrolytic cell. Evaluations of oxycarbonate materials for chlorination wiih varying chlorinating agents were made, and many of the variables such as water content and CO/sub 2/ values were established. Extremely ductile rods were obtained from the direct extrusion of Th metal powder. Plans were completed for the Mark VI electrolytic cell. Work was continued toward the development of a semi-continuous operating electrolytic cell of 7500-a rated capacity. (D.E.B.)

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The effects of variables on the rate of Purex solvent deterioration were investigated with the emphasis on those deterioration products which cannot be removed by carbonate washing. The deterioration rate was found to be directly proportional to the acid and nitrate ion concentrations, and proportional to the square root of the concentration of nitrite ion. Other observations on the effects of temperature, relative merits of brand name solvents, and the effects of radiation are included. A method of calculating the equilibrium level of the solvent deterioration products based on study conclusions and various estimates is outlined. (J.R.D.)

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This document presents a summary of work and progress at the Hanford Engineer Works for April 1955. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

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The production of U/sup 232/ in the cost optimized TBR and oneregion thorlum oxide-uranium oxide slurry reactor has been estimated to be, respectively, 40 and 260 parts per million parts of U/sup 233/ produced. These production rates are compared with corresponding production rates in irradiated thorium rods and found to be comparable. Recommendations are made for increasing the purity of the U/sup 233/ product. (auth)

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Subjects discussed include uranium structure, stability under irradiation, cold working of surfaces, deformation, hollow slugs, grain size, canning, etc.

This report addresses the APPR critical experiment program meeting.