A previous report described the conceptual design of a plutonium producing reactor that may be characterized as follows: Power output (2000 MW); cooling - (natural convection of light water through the reactor, up through a draft tube to an evaporative cooling pond, then back to the reactor, and fuel (400 to 500 tons of uranium enriched to 1.2% U-235). Because this reactor would be cooled by the natural convection of light water, it is believed that the construction costs would be significantly less than for a Savannah or Hanford type reactor. Such expensive items as water treatment and water pumping facilities would be eliminated entirely. The inventory of 500 tons of slightly enriched uranium, however, is an unattractive feature. It represents not only a large dollar investment but also makes the reactor less attractive for construction during periods of national emergency because of the almost certain scarcity of even slightly enriched uranium at that time. The Atomic Energy Commission asked that the design be reviewed with the objective of reducing the inventory of uranium, The results of this review are given in this report.

Report presenting an investigation in the transonic blowdown tunnel to determine the effects of variations in inlet lip swagger from 0 to 60 degrees on the internal-flow characteristics of an unswept semielliptical scoop-type air-inlet model without boundary-layer control. Tests were made for a range of Mach numbers and mass-flow ratios. Results regarding the flow over the fuselage nose, total-pressure recovery at inlet, flow distortions at inlet, and inlet-design considerations are presented.

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The leakage of electricity aoross a vacuum space in an electrostatic generator which employs a mixture of Sr/sup 90/ and Y/sup 90/ as the source of charging current was investigated. The vacuum is obtained by means of an oil pump. The leakage was shown to consist of a flow of positive and negative particles between the anode and the cathode. The positive particles were found to be primarily organic ions produced in a layer of oil on the surface of the anode. The negative particles were shown to be mostly electrons. Yields of secondary negative particles and secondary positive particles produced by average positive particles in the energy range from 50 to 200 kev were measured. Yields were found to be dependent on the nature of the target material as well as on the energy of the incident ion. A mass spectrometer was employed to study the nature of the positive ions. Most of these were charged fragments of organic molecules. Neutral particles were attributed to dissociation of a portion of positive ions during their flight from the anode to cathode. Electrons, most of which originate at the beta source, are presumed to be the agent for positive ion production. …

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Report presenting an investigation of the static longitudinal-stability characteristics of a 45 degree sweptback wing-fuselage configuration with and without a sweptback horizontal tail for a range of angles of attack and Mach numbers. Special focus is given to the pitching-moment characteristics, location of the aerodynamic center, and slope of the lift-coefficient curve.

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A report about elevated-temperature properties of dilute uranium-aluminum and uranium-zirconium alloys. Hot-hardness measurements show that small amounts of wither aluminum or zirconium increase the hardness of uranium at elevated temperatures.

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A new gas-liquid countercurrent system (the ANCO system from Anisole-Complex) for the enrichment of boron isotopes has been developed. It is believed that use of this systems will result in a considerably lower unit cost for enriched boron-10 than was previously possible. The system utilizes the exchange reaction between BF3 (gas) and BF3·anisole (liquid) to concentrate boron-10 in the liquid phase. The single stage isotopic separation factor for this system has been found to vary from 1.039 at 0°C to 1.029 at 30°C. The isotopic exchange reaction has been shown to be rapid. Vapor pressures of the complex as a function of temperature have been measured and the heat of formation of the complex determined. Laboratory experiments show that quantitative removal of the BF3 from the complex can be accomplished by heating. A complete miniature ANCO plant was constructed and operated in the laboratory to test the feasibility of the system. The system was found to operate efficiently with a minimum of attention, and to enrich the isotopes of boron as expected. Based upon the experience obtained with the laboratory ANCO unit, a pilot plant large enough to utilize a 6-inch diameter exchange column was designed. The design calculations of …

Ninety-two thorium slugs were irradiated in the Hanford piles to study the dimensional stability of the metal. The burnups that were incurred covered the range from 300 to 2800 ppm of the Thin. Slugs with burnups as high as 800 ppm were examined for visual and dimensional changes. The dimensional stability of these slugs was excellent, and no signfficant corrosion occurred on the aluminum cans. A cursory examination of slugs with burnups of greater than 800 ppm showed no gross dimensional instability. (auth)

The design, selection, and calculation of the Army Package Power Reactor shielding are described. The APPR-1, a prototype of a package reactor for remote locations, has a primary shield of Fe and water. This shield has been adopted to permit fast erection and to provide low transported weight. Economically, including transportation cost, the Fe--water shield is better thnn a Pb--water shield and is competitive with a concrete shield for a remote site. Because of its location at Fort Belvoir, Va., the shielding requirements for the APPR-1 are considerably more stringent than those for a reactor at a remote base. Since the secondary shielding which surrounds the entire primary system must provide protection for personnel at any location outside the vapor container, concrete is provided for this need. (auth)

Abstract. The design, selection, and calculation of the Army Package Power Reactor shielding are described. The APPR-1, a prototype of a package reactor for remote locations, has a primary shield of iron and water. this shield has been adopted to permit fast erection and to provide low transported weight. economically, including transportation cost, the iron water shield is better than a lead water shield and is competitive with a concrete shield for a remote site. Because of the location at Fort Belvoir,Va., the shielding requirements for the APR-1 are considerably more stringent than those for a reactor at a remote base. Since the secondary shielding which surrounds the entire primary system must provide protection for personnel at any location outside the vapor container, concrete is provided for this need.

The background for the conference is given. Plenary sessions papers are abstracted but discussions are quoted. Lists are included of technical sessions, U.S. papers, organizations, delegates, exhibits, with some pictures included, contents of the technical library and films available. Press releases are reported. Also included are two U.S. brochures prepared for the U.S. Exhibit, ''United States Research Reactor'' and ''Techical Exhibition of the United States of America.''

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Memorandum presenting tests at two supersonic speeds to obtain experimentally the aerodynamic damping characteristics of a control surface on a two-dimensional wing. The control surface had a chord of 1.67 inches and a span of 7.25 inches and was supplied in three materials with different mass, inertia, and stiffness properties. Results regarding the presentation of data and comparison with theory and comparison with control-surface data for a triangular wing are provided.

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For some time, it has been the opinion of the personnel of this laboratory and other investigators that an appreciable amount of the corrosion observed on stainless steel in nitric acid solutions might be due to the presence of some of the lower oxides of nitrogen; NO-, NO-2, etc. If this assumption is correct, the elimination of these compounds from process solutions should result in a significant increase in the service life of equipment handling nitric acid, such as acid fractionators. Since the corrosion problems experienced in acid fractionators and concentrators are very severe, an investigation of this theory becomes highly desirable. The purpose of this report is to summarize the work performed, to date, by this laboratory in the investigation of the inhibition of nitric acid corrosion of stainless steel.

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