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This report provides the weather that pilots observe while in flight.

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.

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.

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

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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This technical report represents a brief survey of work by this project on the effects of ultraviolet radiation (UV) on certain of the photochemical and metabolic properties of rhubarb chard and sugar beet (Beta vulgaris). These plants were selected for this work because for some years they have been used as sources of chloroplasts for Hill reaction studies in this laboratory. Some of this work has appeared as a brief paper.

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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 …

A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.

The purpose of this report is to present a HAPO proposal for the design and construction of a high-temperature, high-pressure light water recirculation test facility for the Westinghouse Electric Corporation, Atomic Power Division This report does not attempt to justify the feasibility of site location nor does it attempt to elaborate on such technical considerations as permissible test specimen heat generation and enrichment requirements which have been covered in an earlier document. Instead, detail information is developed on the proposed design with major emphasis on detail descriptions of the proposed loop and auxiliaries, design and construction scheduling and costs, and operating costs.

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Estimation of internal facilities required in the high-flux pile for research on materials for power-producing piles and components.

Report issued by the Brookhaven National Laboratory discussing the area survey manual covering the 15 service stations. Design and operations of the service stations are presented. This report includes tables, illustrations, photographs, and a map.

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).

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 …

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.

This report presents the details of the operations of the Savannah River Plant manufacturing division during the month of January 1955.

This report presents the details of the operation of the Savannah River Plant manufacturing division during the month of May 1955.

"A wind-tunnel investigation was made to determine the effects of ejecting high-velocity air near the leading edge of plain trailing-edge flaps on a 35 degree sweptback wing. The tests were made with flap deflections from 45 degrees to 85 degrees and with pressure ratios across the flap nozzles from sub-critical up to 2.9. A limited study of the effects of nozzle location and configuration on the efficiency of the flap was made. Measurements of the lift, drag, and pitching moment were made for Reynolds numbers from 5.8 to 10.1x10(6)" (p. 1).

"Aerodynamic forces and moments have been obtained in the Langley 9- by 12-inch blowdown tunnel on an external store and on a 45 degree swept-back wing-body combination measured separately at Mach numbers from 0.70 to 1.96. The wing was cantilevered and had an aspect ratio of 4.0; the store was independently sting-mounted and had a Douglas Aircraft Co. (DAC) store shape. The angle of attack range was from -3 degrees to 12 degrees and the Reynolds number (based on wing mean aerodynamic chord) varied from 1.2 x10(6) to 1.7 x 10(6)" (p. 1).

"Low-lift drag data are presented herein for one 1/7.5-scale rocket-boosted model and three 1/45.85-scale equivalent-body models of the Grumman F9F-9 airplane, The data were obtained over a Reynolds number range of about 5 x 10(exp 6) to 10 x 10(exp 6) based on wing mean aerodynamic chord for the rocket model and total body length for the equivalent-body models. The rocket-boosted model showed a drag rise of about 0,037 (based on included wing area) between the subsonic level and the peak supersonic drag coefficient at the maximum Mach number of this test" (p. 1).