Report presenting an investigation of the low-speed static stability characteristics of a complete model equipped with a W wing. The lift-curve slope of the wing-fuselage combination was found to be in good agreement with that predicted by available wing-alone theory. Results regarding the longitudinal characteristics, wing-juncture modifications, and lateral and directional stability characteristics are provided.

The Reactor Safeguard Committee formula for the allowable minimum distance between a reactor and the public domain is expressed as: r = 0.01{radical}P, where r = radius from reactor in miles, and P = reactor power level in kilowatts. The six plates in this report illustrates the application of this formula for Hanford Works, both for individual reactors and all reactors in an area.

This document is a compilation of obsolete security codes, convenience codes and local jargon in use, or previously used, at Hanford Works. It is compiled to aid readers in understanding the Hanford report literature, particularly that originated in the early years of the Project.

The performance of a 16-stage axial-flow compressor, in which the mean-radius solidity was reduced from 1.28 to 1.02 in the fourteenth through sixteenth stage rotors was determined. The performance of this modification was compared with that of the compressor with original rotors. The reduced solidity resulted in slightly improved performance.

Eleven thorium-carbon alloys in the range 0.02 to 2.0% carbon were prepared by vacuum-arc melting. The hardness varied from 19 R/sub A/ for the 0.02% alloy to 108 R/sub B/ for the 2.0% alloy. The preparation of thorium- chromium alloy was hampered by a reaction with the zirconia molds, which results in porosity in the casting. The failure of aluminum-silicon bonded X-10 slugs after heat treatment for seven days at 400 deg C was traced to the failure to remove tin after the tin dip and the presence of a gas during heat treatment. Tensile tests were made on extruded thorium, and no correlation was found with extrusion variables. A composition effect was found, however, which showed a linear relationship between carbon content and tensile strength. Creep tests on thorium, uranium, and Inconel continue. The program of evaluating the variables in the fabrication of clad fuel elements, using MTR techniques was concerned mainly with the distribution of UO/sub 2/ in the core compact, the temperature of rolling, and the particle size of the metallic core powder. Progress is being made in the preparation of three-layer laminates without the use of a protective can during the hot-rolling operation but with the …

This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses thorium research, the mechanical properties of metals including thorium, uranium, inconel, and z-nickel, the ANP program (including the following topics: the physical chemistry of liquid metals, and welding research), and the materials testing reactor program.

This is a progress report of the production reactors on the Hanford Reservation for the month of April 1952. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

Report presenting testing of a parabolic body of revolution in the 4- by 4-foot supersonic tunnel at two Mach numbers. The investigation included the effects of Reynolds number, fins, internal contour of body base, and two support systems on body pressure and force drag at an angle of attack of 0 degrees.

Report presenting an investigation to determine the effect of systematic variations in inlet-air and fuel parameters on the smoking characteristics of a single tubular turbojet-engine combustor. The most pronounced effect on smoke was observed with increase in inlet-air pressure which produced large increases in smoke concentration. Results regarding the reproducibility of smoke measurements, effect of fuel-air ratio and inlet-air parameters on smoke density, effect of fuel parameters on smoke density, full-scale engine tests, and combustion efficiency are provided.

This report describes the manufacture of 25 Aluminum clad, 10 w/o plutonium-aluminum alloy and 5 w/o plutonium-aluminum alloy cored specimens for Argonne National Laboratory-University of California irradiation tests in the Materials Testing Reactor. The manufacturing method: preparation of cores and cladding material, assembly and welding of compacts, outgassing, roll bonding, shearing, identification marking and final fabrication into napkin "rings" is described in detail. Of ninety-six specimens fabricated, ninety-one were completed as finished specimens. Forty-four of these contained 5 w/o plutonium alloy cores and forty-seven contained 10 w/o plutonium alloy cores. Five specimens ere rejected for bond blistering.

Report presenting an investigation into the effects of interference at supersonic speeds on the aerodynamic properties of wing-body combinations to determine the pitching moments. The correlation points of various wing-body shapes are provided and suggestions for modifications are made.

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Report presenting an investigation of the properties of molybdenum disilicide in which a fine-grain material and a large-grain material were produced using different methods. Results regarding the fine-particle sintered material, coarse-grain, hot-pressed material, a comparison of the two materials, and the effect of oxygen on sintering and mechanical properties are provided.

Report presenting a free-flight investigation of drag on four full-scale models of 16-inch-diameter ramjet engines over a Mach number range of 0.6 to 1.43. Data was obtained at different internal airflow rates by inserting annular restrictors in the outlet of the models. Results regarding the variation of the total-drag coefficient, effect of Mach number on drag coefficients, and magnitude of drag coefficients are provided.

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The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.

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From introduction: "Analytical procedures for the determination of plutonium samples from the extraction and concentration plants utilize the carrying of the hydroxylamine-reduced trivulent plutonium by coprecipitation on lanthanum fluoride. Most other plutonium procedures also take advantage of the efficient carrying on lanthanum fluoride."

From abstract: "Two samples, each containing an estimated 10 curies (2 mg) of polonium-210, were purified by vacuum distillation and evaporated onto oblique sections of X-ray targets made of copper. Four lines of the K series and ten lines of the L series of the X-ray spectrum of polonium were recorded with a one-meter transmission crystal spectrograph and a 25-centimeter Bragg spectrograph, respectively. Measured wavelengths agree approximately with values predicted by extrapolation of Moseley's law and with those claimed by Hulubei. Decay of polonium-210 (half life = 138 days) and growth of lead-206 (stable) were observed over a period of 180 days."

The following document describes observations from tests on neptunium metal and their reactions to different room temperatures.

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Radioactive decay data are used to calculate the atomic masses of the heavy isotopes, A> 203. The four radioactive families are then connected by means of neutron binding energies known from reactions on various isotopes. Finally all the masses are collectively adjusted for the best fit with mass spectrographic information available in this region. The masses so calculated are presented. Differences between masses of isotopes are estimated to have an of (plus/minus) 0.00020 mas units or about 200 Kev; the position of the masses taken collectively is in doubt by about 1.5 Mev.

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Technical report on the geological investigation of the Green River desert area, Utah, studying uranium deposits in the area.