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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.

It is recommended that the Design Committee approve the installation of a refrigeration system in the 105-C gas circulation system for removal of moisture from the reactor following a process tube leak as was previously approved by the C-431 Project Committed. Engineering studies show that this refrigeration system is necessary to provide sufficient water removal capacity in order that the water absorbing capacity of the system furnished by the silica gel towers will not be a limit to the rate at which a reactor can be rehabilitated following a serious leak.

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.

Five telescope actuator systems designated as ``R``, ``P``, ``L``, ``K`` and ``C`` were fabricated at New York Ship. All five were similar in specifications except for minor detail. For overall assembly refer to du Pont arrangement drawings W-153422, W-153423, and W-153424. These drawings illustrate ``R`` unit; however, they are representative of all units. They show a complete listing of material required and an overall view of the telescoping assembly. Since jigs and special tooling were set up to conform to a definite deck plate fabrication sequence, the inspection procedures and methods described in this book will follow logically the fabrication steps.

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In this report, a brief discussion is given for each of the following activities under study during this period: xenon generator; C{sup 12} cross sections; critical mass problems (for process vessels in Bldg. 231); neutron beam catcher design; neutron diffraction spectrometer; beta spectrometer; hollow slug program; instrumentation; blackness corrections; exponential pile measurements with small slug size; critical lattice experiments; lattice theory; and radiation damage.

The hot pressing die successfully bonded a composite of Ni plate U and Al. A die for step processing is being fabricated. Cu and Mg additions to the AlSi bath lower the dipping temperature but increase intermetallic formation with ductility loss. Optimum dipping rate for continuous AlSi coatings has been established. Extrusion of Al over a cylindrical core was successful. 7.5% Zr-U is not sensitive to oxygen content under crevice corrosion in boiling demineralized water. A method was developed for monitoring the progressive deterioration of bond layer in boiling water by resistivity data; results confirm that the Cu bond is not as corrosion resistant as Ni or AlSi. Two nondestructive methods were developed for thickness of electroplated Ni on U.

The objective of this test is to evaluate the effects of low pH process water and unfiltered river water on pile operation. This report is dated September 21, 1953.

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The hiring schedule was reviewed by the same method that was used in the reference letter with essentially the same results; that is, that we should hire approximately 125 technical graduates during the hiring year 1953-54. In the belief that possibly this method was a bit too crude for this stage of the Plant development, I have applied another one, which I believe is fairly independent of the previous method of calculation since it is directed at a consideration of only people required who have a technical background.

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This report describes work within the applied research section of the physics group at Hanford during June 1953, both experimental and theoretical. It includes work on carbon 12 thermal neutron cross sections, tritium conversion efficiency, critical mass studies, fission cross sections of Pu-239 and U-235, studies of exponential piles and slug buckling, theoretical studies of lattice experiments to study neutron fluxes, and studies of radiation damage effects on thermal conductivity of graphite.

During the meeting each of the bonding mechanisms under study at BMI was reviewed by the engineer directly responsible for the work. These methods were solder bonding, extrusion cladding, roll cladding, and pressure bonding. The pressure bonding method, using an electroplated copper bonding layer, appeared to be most suitable for immediate use in MTR test plates. Roll cladding appears feasible only if further work indicates that bonds can be obtained either at temperatures in the high alpha range or using low deformations. Extrusion cladding is in a preliminary stage ad requires considerable development before being considered as a production technique. However, it was felt this last method is promising and offers the highest production speed of any under consideration. A brief discussion of the corrosion of the 5% zirconium-uranium alloy resulted in the conclusion that, because of the tendency toward crevice attack, work in this field should be diminished and no new projects started.

This report describes the objective of this production test which is to simulate with a few tubes operation of the old piles with small water annulus at power levels in the range of 800--900 MW.

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Attention has continued to be concentrated on routes employing either wrought uranium or powder metallurgy product for the making of flat plate fuel elements of approximately 0.180-inch uranium metal core thickness bonded to either ribbed or ribless aluminum sheaths. Intermediate goals of the program are to have elements 18 inches long for MTR irradiation tests this fall and to make sufficient advance in the overall program in 1954 so that an initial reactor charge of 15-foot long fuels can be provided as early as possible in 1955. The development of a satisfactory process tube for retaining an assembly of several fuel elements is also required. Uranium of satisfactory quality for fabrication into fuel elements appears to have been produced by the August high alpha rolling at Superior Steel, and it seems likely from the electroplating results that the metal can be employed for electroplating and bonding without such surface preparation as vapor blasting, grinding, or machining. Difficulty in obtaining aluminum components, both sheaths and process tubes, remains a bottleneck in the development program and specifically has delayed work on the wrought metal samples for MTR tests.

The visit was made to discuss progress on bonding and cladding of extended surface fuel elements.

Agreements reached on security include classification and security regulations. Safety agreements include a problem with excessive heat in the metallurgy section. Other topics discussed include Building 777, CMX, hydrisides, and separations. Appendices include information on financial status and the status of technical division studies.

This memorandum discusses four photographs of Failure 250, from Tube No. 2179-C, which are presented to show the type of failure as viewed in the 111-B cave. The first three photographs are successive rotations of the slug, illustrating the split-out portion at the base end of the piece. The fourth photo was focused on the split to show the bulging of the slug and the width of the opening.

The investigation reported in this document concerns itself with studies of the mechanism of corrosion on the exterior of process tubes and with studies of the protective qualities of anodic films which might prevent corrosion on the exterior of process tubes. Sections of process tubing coated with Aqua-Dag, a colloidal graphite suspension, were included in these tests for comparison purposes as present operating procedures call for the application of Aqua-Dag to the exterior of process tubes for lubrication purposes during the charging of tubes into the piles.

Between June and August, 1952, a series of leaking process tubes were discovered in F and D Piles. All of the tubes, six from F and two from D, were removed and found to be leaking from a pitting attack that progressed from inside the tube walls. During this same period a serious slug pitting attack, not previously observed, was found on many slugs discharged at F Pile. Two hypotheses were presented that were considered that most likely explanations of the observed corrosion effects. The first mechanism-presented involved the process of cavitation. Briefly this hypothesis proposed that an obstruction to the water flow in the slug-tube annulus, such as a cocked slug or partially plugged annulus, caused the formation of a low pressure area capable of sustaining water vapor formation. The water vapor thus formed moved into the undisturbed, or higher pressure, regions of the annulus with the subsequent collapse of the vapor bubbles. This mechanism weakened or destroyed the protective oxide coat on the slugs and tubes, producing a localized corrosion phenomenon. The second hypothesis proposed to explain the observed effects was the erosion-corrosion hypothesis. This hypothesis presented the mechanism of protective aluminum oxide coat removal by the abrasive …

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The potentialities of unfiltered Columbia River water as a pile coolant have been discussed in a recent survey of the available information on the subject. The survey report points out the gains which the use of unfiltered water offers, and proposes a logical framework of treatment by chemical additives which appears to have a reasonable probability of successfully developing a far less expensive pile coolant. A comprehensive testing program is now being initiated to obtain the required experimental information concerning the effects of unfiltered water on corrosion, film formation, and effluent activity. The purpose of this report is to outline the range of variables to be studied; to discuss the various experimental techniques to be used; and to establish the anticipated scheduling of the several phases of the program.