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One uranium tensile specimen irradiated to 620 MWD/T (1.75 x 10{sup 20} nvt) was tested at 285 C (545 F). The values obtained were: ultimate tensile strength 71,000 psi, 0.1% offset yield strength 70,000 psi, percent elongation (one inch gage length) 0.7, and modulus of elasticity 12 x 10{sup 6}. These values are comparable to the as-irradiated values of specimens tested at room temperature which were: ultimate tensile strength 76,000 psi, 0.1% offset yield strength 71,500 psi, and percent elongation (one inch gage length) 0.36. The elongation of the specimen tested at 285 C was less than that of a specimen annealed at 700 C (1290 F) after irradiation, then tested at room temperature. Experiments have been initiated to determine the structural stability of irradiated uranium-silicon alloy when this alloy is in the stable epsilon phase. Present work is limited to the evaluation of thermal expansion as a criterion for degree of epsilonization. This technique has not proven satisfactory. The damage resulting from the bombardment of uranium with electrons in the 1-2 MEV range is to be evaluated using electrical resistivity and x-ray diffraction to determine the extent of the damage. Calculations indicate a threshold energy of about 1.25 MEV …

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Nine technical studies were approved for funding. Discussions at the meeting centered around safety and work schedules. Appendices contain information on Financial status, the Separations program, the Analytical Chemistry program, and the Technical Division studies that were approved at the meeting.

Major additions to separations facilities may be required because of increased reactor power levels, reduced exposures; changes in slug specifications, obsolescence of existing solvent extraction plants or development of new separations processes with lower operating costs. The magnitude of first costs for a separations plant is so large as to discourage production planning which would require an additional major separations facility. Experience in separations design has shown that certain process and equipment changes, if they could be developed, would significantly reduce the capital investment in a separations facility. Accordingly design development for a new separations facility is under way. The purposes of this document are to present the results of the first separation design study directed toward a new solvent extraction plant and to summarize process, plant, and equipment changes which should be developed to achieve significant capital and operating cost reduction.

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W. J. O`Leary and R. R. Herries visited BMI to review the progress of subcontract research on extended surface fuel elements and on consolidation of Horizons` thorium. 1. Corrosion samples, 1in. diameter {times} 0.180in. thick nickel-plated uranium, which had been press-clad with aluminum at 510{degree}C and 6000 psi, have been on test for 18 days with no evidence of undercutting. Similar samples press-clad with 10,000 psi have been exposed for 7 days with no failures. 2. The hydrogen and chlorine content of as-received Horizons` electrolytic thorium was greatly reduced during vacuum sintering and arc melting. 3. A second lot of Horizons` thorium has been compacted and sintered to provide electrodes for two 9-10 lb. melts. 4. Diffusion couples are being annealed and examined in order to determine the rate of solid solution diffusion of thorium in aluminum.

W.J. O`Leary and R.R. Herries visited BMI in company with C.C. McBride, SRL, to discuss the results of subcontract research on the extended surface fuel element program and to discuss with BMI personnel the programs included in the recent contract extension. A summary of results are given in the following. Double and triple melts from two 9--10 pound ingots of arc-melted Horizon`s thorium showed decreasing porosity. Physical and chemical data, on these as well as on eight previous double melted ingots, are being obtained. The problems involved in obtaining uniform castings of uranium-aluminum alloy for co-extrusion billets were discussed, with emphasis upon those phases to be investigated at BMI. A program was outlined to evaluate the effects of outgassing, by vacuum annealing, on the corrosion resistance of nickel-plated uranium. Data obtained from diffusion studies at BMI show that the mutual diffusion at high temperatures of thorium and aluminum is slow, with the diffusion of the thorium into the aluminum proceeding somewhat faster than that of the aluminum into the thorium. Possible methods of applying an inner cladding of aluminum to a tubular uranium fuel element were discussed. ``Half-dollar`` size uranium corrosion samples, nickel-plated and press-clad with 30-mil aluminum at 10 …

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Nuclear parameter variations are presented for sodium graphite reactors using Pu-spiked natural U as fuel. The fuel feed is assumed to be natural U, and the important variables are the initial amount of excess reactivity, lattice spacing, and alpha , the ratio of Pu/sup 239/ to U/sup 235/ in the feed material. The system is called "steady state" in that the ratios, N/sub 40/N/sub 49/ = sigma /sub c(49)// sigma /sub a(40)/ and N/sub 41//N/sub 4 9/ = sigma /sub c(49)/ / sigma /sub a(41)/, obtained from setting the build-up equations to zero are assumed for the feed concentrations, and the feed material to the reactor is always the same. During irradiation, the U/sup 235/ and U/sup 238/ concentrations steadily decline while the Pu isotope concentrations initially increase, then decline. To ensure sufficient plutonium for feed material, it is necessary to remove the fuel from the reactor before the Pu content drops below its initial value. Although the reactivity variations presented were calculated specifically for sodium graphite reactors, they may be applied to any thermal reactor using Pu-spiked natural U as fuel. The reactivity changes are determined primarily by the fuel characteristics and are only slightly dependent on the other …

This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their maximum potential power levels because of a limited availability of process cooling water. As a result of this program, it is estimated that 1650-2350 megawatts of total additional production will be achieved.

This document has been written because of a request for information from the Advisory Committee on Reactor Safeguards. Hanford operating experience has been summarized in terms of operating hours, startups and scram analysis.

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Production rates of the Hanford reactors can be increased in proportion to the quantity of process cooling water which can be supplied to them. This water must be of such a quality that slug and tube corrosion rates are acceptable, the gross activity of the effluent water must not be excessive, the concentration of specific radioactive isotopes constituting a radiological hazard must be minimized, and the film formation rates should be as low as possible. In the Hanford water treatment process, the filter plants are the controlling factor in determining the quality of the water, and one of the elements limiting the quality of water. A major development effort was therefore undertaken to develop methods of increasing the capacity of the existing filter plants. This report presents the result of this development work from its inception in 1951 to its conclusion in 1954.

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This document details activities of the Hanford Atomic Products Operation (HAPO) during 1954.

This document from Savannah River Plant reports progress for June 1955 in the 100, 200, 300, and 400 Areas. Information is presented on the assembly area, reactor control, reactor complex, and disassembly for the 100 Area (reactors). From the 200 Area (separations plants), progress at the solvent extraction plants is reported. Uranium - Aluminium and thorium canning are reported for the 300 area (reactor fuels fabrication). And stainless steel corrosion studies are reported for the 400 area (heavy water).

Study approvals are listed for Studies 8506, 8509, 8518, 8519, and 8520 with man-months and program dates specified. Safety and security agreements are listed. Additional topics discussed are: financial status, experimental physics programs, pile engineering division program, and technical division study status.

Study approvals are listed with man-months and date specified. Information and safety agreements were reached. Occupational safety and radiation protection, fuel slug development, instrumentation, ingot rolling, and security violations are discussed topics. Appendices contain information on financial status, pile materials program, instrument development program, and technical division study status. (GHH)

This document is the April 1955 Monthly Report of the Process Section/Manufacturing Division at the Savannah River Plant. It contains information on activities in each of the SRP areas (100-400 areas), as well as on utilities and general services.