A compilation is given of analytical procedures used in the laboratory- scale separation of radium from sulfateinsoluble residues from African pitchblende processing. Included in five alternate procedures are quantitative analyses for silica, lead, copper, molybdenum, barium, nickel, calcium, magnesium, radium, moisture, water-solubles, nitrate, silver, manganese, zinc, carbon dioxide, sulfate, and chromium. (auth)

This report discusses the presence of corrosion products upon aluminum process tubes removed from wet portions of F Pile which led to the suspicion that the tubes might be corroding at an accelerated rate because of water entrapped in the channels between the tubes and the graphite blocks. Corrosion was especially noted on those tubes that were tightly stuck within the blocks. Analysis of the corrosion products showed that the major constituent was a hydrated aluminum oxide, containing iron oxide, calcium carbonate, and other substances in lower concentrations. This led to placement of an order for the anodizing of 200 process tubes.

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Annual report of Brookhaven National Laboratory describing the work and findings for the lab's departments during summer 1951-1952.

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This memorandum discusses slug rupture frequency which appears to be a factor that may limit the power level of C Pile. Since additional exposure of Group 8 uranium slugs has increased the available information on the behavior of material similar to that which will be charged into C Pile, a review of this tube power limitation has been made. Utilization of additional data has been possible by use of the revised method of calculating rupture rates discussed in reference (2).

The test established that a practical orifice selecting device can be made and used to control the water flow rate to a process tube at either of two accurately calibrated rates with no loss of accuracy in flow measurement. With the selector tested, there was no flow restriction during the orifice transition. The pressure fluctuations during the change were small in magnitude, and caused no operational problem. The test demonstrated that orifice selection is feasible from operating other factors justify their use.

This document presents a summary of work and progress at the Hanford Engineer Works for August 1952. 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` section summaries 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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Fission product activities and heat generated by fission product decay as a function of time, in waste solutions obtained by processing uranium irradiated under the present Hanford schedule, were calculated. From these data, curves showing expected heat evolution in stored Redox Process Wastes, during and following filling of the waste tanks, were prepared assuming various modes of operating the plant and various production rates. Total heat available for evaporation of water from the tanks was also determined. Under the most favorable plant operating conditions considered, calculated heat available for evaporation will be sufficient to reduce the waste volume by a factor of two. Experimental work showed that the wastes may be reduced in volume (evaporation) by a factor greater than four. Thus, supplemental heat would be required to attain the maximum volume reduction.

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High energy p-p scattering has been interpreted by several authors in terms of highly singular noncentral interactions. The triplet state calculations were carried out in the Born approximation and, together with the singlet, yielded an almost isotropic (c.m. system) differential cross section. Agreement with experiment was good at large angles but the theoretical peak in the forward direction, due mostly to singlet d scattering, was too large. It is not clear however that the Born approximation should be valid for singular potentials.

Thorium Research. The effect of quenching temperature on the hardness of Th--C alloys is described. The effect of quenching temperature and oxygen content on the hardness of Th--O, alloys is discussed. The effects of Be, Cr, and C additions on the properties of pure Th are described. The mechanical properties, recrystallization, and fabrication of Th are given. Preferred Orientation of Uranium. Fabricating conditions, preferred orientation, and examination of alpha-extruded U rods are given. The creep rate of beta-treated normal U and of extruded Th is given. Properties of some high-temperature brazing alloys are given. Welding conditions are given for cone-arc welding of stainless steel tube-to-header joints. Homogeneous Reactor Program. Analysis of various compacts containing B/sub 4/C are given. Preliminary work on the variables involved in welding Ti was started. Experimental work to determine the effects of various impurity elements on the impact properties of Ti and Zr was started. A metallographic examination of Ames Th cold worked and annealed for 60 minutes is presented. Experimental Plate-Cladding Program. The cladding of Th and U with Zr is discussed at length. The cladding of Th with Al is described. Experiments on welding of Th, U, and Zr plates are presented. (W.L.H.)

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The separation of the phenomenon of photosynthesis in green plants into a photochemical reaction and into the light-dependent reduction of carbon dioxide is discussed, The reduction of carbon dioxide and the fate of the assimilated carbon were investigated with the help of the tracer technique (exposure of the planks to the radioactive C{sup 14}O{sub 2}) and of paper chromatography. A reaction cycle is proposed in which phosphoglyceric acid is the first isolable assimilations product. Analyses of the algal extracts which had assimilated radioactive carbon dioxide in a stationary condition ('steady-state' photosynthesis) for a long time provided further information concerning the proposed cycle and permitted the approximate estimation, for a number of compounds of what fraction of each compound was taking part in the cycle. The earlier supposition that light influences the respiration cycle was confirmed. The possibility of the assistance of {alpha}-lipoic acid, or of a related substance, in this influence and in the photosynthesis cycle, is discussed.

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This memorandum discusses the engineered safety system which combines the Ball 3-X System with the VSR System. The operation of the system is detailed and settings are recommended for 105-C trips.

The present RMA Line has now progressed through the run-in period and is engaged in actual production. Considerable new data and experiences are available for use in an evaluation of the basis used for design of the equipment in regard to contamination control and the safety of operating and maintenance personnel. Research and development funds have been allocated to the improvement of the 234-5 process equipment. Thus it is desirable that an up-to-date basis be established for use as criteria for the design development of these improvements. It is concluded that remote control operation of all plutonium purification and fabrication equipment is ultimately desirable. However, until reliable, tested, remote-control equipment is available, the remote control requirement may have to be compromised on some steps of the process to allow non-remote or rubber glove operation in order to obtain equipment with sufficient operating reliability.

A representative series of aircraft which could be powered by a relatively low-temperature liquid-coolant-cycle nuclear power plant are described. Present aircraft such as the B-36, B-52, and B-47 bombers as well as new designs were investigated. Design and performance characteristics of all the aircraft are presented.

This memorandum details the recommendation of the Technical Section that the C Pile be started up using alum treated water to which has been added sodium dichromate at a concentration of 2 ppm., and that the pile be purged at monthly intervals despite the expected absence of film formation. During the initial months of operation the necessity of adding sodium dichromate and of purging the pile should be evaluated with the hope that these factors can be eliminated from the process. The reasons for this recommendation, and proposals for water treatment in the current operating piles are discussed.

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