Report presenting the X-3 airplane, which has a straight 4.5-percent-thick wing of modified hexagonal section, which has been flown to maximum wing normal-force coefficients in the Mach number range from 0.7 to 1.1 at an average altitude of 30,000 feet. Measurements were made of airplane and wing-panel maximum normal-force coefficients and of some buffeting characteristics.

The compositions of the compounds and fused salt mixtures referred to in the ANP project by numbers are given.

Report issued by the APDA regarting studies conducted on the state of uranium at different temperature and pressure. Calculations are presented for the differing pressures of uranium; it includes tables.

Report presenting tests of an airplane model equipped with missiles to investigate the capability of that combination to achieve satisfactory launching and jettisoning of the missiles. Information about pylon modifications, missiles in launch positions, missile trajectory, and missiles in jettison positions is provided.

Report presenting the performance of two translating-double-cone inlets with contrasting rates of turning on the spike shoulder and corresponding cowl projected frontal areas of 40 and 20 percent of maximum compared over a range of Mach numbers. Results regarding internal-flow performance, external-flow performance, inlet airflow patterns, and propulsive-thrust comparison are provided.

A parameter survey was conducted on the Organic Moderated Reactor (OMR) to determine the nuclear effect of temperature, enrichment, fuel to moderator volume ratio, fuel element size, ard fuel element container variation. Temperatures ranged from 300 to700 deg F; enrichments from 1.5 to 1.9%; and fuel to moderator volume ratios from 0.1333 to 0.545. Fuel element sizes of 3.75, 4.5, and 5.5 in. were considered. The stainless steel fuel element container thickness was varied from 20 to 80 mils, and also 200 mil aluminum was substituted for the steel. Results were obtained as values of k/sub eff/ which ranged from 0.927 to 1.152 through 150 problems. It was concluded that fuel element size should be at least 4.1 inches, fuel to moderator volume ratio in the neighborhood of 0.30, and enrichment 1.7% assuming 8% excess k for poisoning, burnup, and control. (auth)

Research directed toward an evaluation of a reflector control scheme for a small boiling heterogeneous reactor is reported. The control method uses the ambient reactor steam pressure to adjust the height of a radial water reflector. Critical-assembly experiments were conducted to measure the reflector worth and the effect of nonhomogeneous voids. The critical-assembly core approximated a right circular cylinder 24 in. high and 21 in. in diameter. The core was made up of polyethylene strips to simulate water channels, aluminum strips, and uranium foil. The reflector consisted of polyethylene blocks and two different densities were used to simulate two different water temperatures. The coldwater, hot non- power-producing, and boiling powerproducing reactor conditions were mocked-up. These conditions were obtained by voiding the moderator plastic strips. The results indicate that sufficient reactivity is available in the reflector to compensate for large power variations and equilibrium poisons. However, the reactivity worth is not great enough in the system considered to include startup from the cold condition or long-time fuel burnup. These experiments also show that in calculatioiis of critical mass and reflector worth the assumption of uniform void distributions seems valid for corcs of the size studied. (auth)

Report presenting an extensive metallographic examination of a group of buckets overtemperatured in service. Most of the buckets showed an overaged microstructure. Results regarding the metallographic survey and stress-rupture tests are provided.

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In homogeneous nuclear reactors significant quantities of radioactive inert gaseous fission products must be separated from the fuel solution for disposal. The present disposal scheme, which is employed on the HRT, is to pass the mixture of fission product gases and oxygen through a charcoal adsorption bed. the oxygen passes through the bed relatively un-adsorbed, but the radioactive inert gases are adsorbed and are displaced from the bed bed very slowly giving the gases a much greater residence time than would exist if no bed were used. This long residence or "holdup" time permits the short-lived inert gases to decay away before emission to the atmosphere and thus greatly reduces the safety hazard produced by disposal of the gases to the atmosphere. The same effect could be obtained by using a large holdup tank, but the charcoal bed is much more compact and thus required less shielding.

Graded nonuniform cartridges are described which have plates with larger holes, greater free area, and/or greater plate spacing. These plates were developed and specified for the Purex Plant A-type columns. Use of the cartridges eliminated cyclic local flooding and increased the complete flooding frequency by 10 and 25 cycles/min at volume velocities of 530 and 1060 gal/hr/ sq ft, respectively, and exhibited satisfactory extraction efficiency over a wide range of frequencies and throughputs. (auth)

This document is a HAPO report dated September 20, 1957. At the time of this report, there had been many different methods suggested for improving the Purex organic recovery system. Some of these suggestions been tried in the plant and others had not. Information concerning this system and, particularly, methods for improving it were wide spread. At the time of this report was no immediate source of information available on the proposed and investigated methods for improving the Purex solvent recovery system.

This document details activities of the Irradiation Processing Department during the month of August, 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and engineering; operations; production and reactor operations; facilities engineering operation; employee relations operation; and financial operation.

This document details activities of the Irradiation Processing Department for the month of February 1957. (FI)

Tests of the HRT fuel and blanket recombiners at several gas concentrations and steam rates disclosed satisfactory efficiency at approximately design conditions. At lower gas concentrations and steam fiow rates a small recombiner downstream from the condenser is necessary to maintain 100% recombination. It is recommended that the platinized catalyst in the fuel and blanket HRT recombiners not be replaced, and that a small recombiner be installed in the 1-in. off-gas line from each recombiner condenser. (auth)

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Stress corrosion was found in 8 components of the HRT mockup; only of four of these actually shut down the loop. All of the failures have occurred in the high-pressure system of the loop.

Report presenting testing of three wings of different aspect ratios at a range of angles of attack to provide information on the effects of large angles of attack on the lift and normal force on triangular wings in a specific Mach number range. Results regarding the comparisons with data from semispan tests, prediction of lift and normal force and comparison with the experiment, and maximum lift coefficient are provided.

The HRT leak detector system consists of four headers each of which are connected on one side to a common supply of pressurized water and on the other side by individual tubing to the ring grooves of approximately twenty flanges. There are two methods of detecting the loss of water that are particularly applicable to the HRT: (1) By the loss of pressure in a constant volume system; (2) By the measurement of flow from a constant pressure system. It was determined to investigate the second method which requires a flowmeter capable of measuring flows of .5 cc or less of water per hour. The experiment flowmeter constructed performed almost exactly as the design calculations predicted.

From introduction: "One of the most important factors which must be considered in the chemical processing of spent fuel elements is the safe and economic disposal of gaseous radioactive fission product wastes given off in the fuel element dissolution operation. For this reason work is underway at ORNL to study the various gas disposal methods that might be used to handle the radioactive fission product gases, krypton, xenon, and iodine."

Purpose: A reconnaissance was conducted during parts of August and September, 1956, of an area about two miles square in the southern Carrizo Mountains where the Permian Cutler formation, including its DeChelly member, and the Triassic Shinarump member of the Chinle formation, are exposed. The purpose was to appraise the uranium potential of the area and to determine the cause of bleaching in the DeChelly. Extensive uranium mineralization in the Salt Wash member of the Morrison formation around the Carrizo Mountaind suggested that the Shinarump, a good producer in other areas on the Colorado Plateau, might be mineralized here as well. Bleaching, as shown in the DeChelly; has proven such a useful guide to uranium at other localities as to merit investigation here.

Report presenting an investigation of the ejection release characteristics of the MB-1 rocket from the missile bay of a model of the Convair F-106A airplane with its fin tips retracted at a simulated altitude of 18,670 feet. Successful ejections of the rocket were made at supersonic speeds by applying a combination of ejection velocity and nose-down pitching moment at release.

Report presenting an investigation of the ejection release characteristics of the MB-1 rocket from the missile bay of a Convair F-106A airplane. Results regarding pitching moment, ejections, release conditions, and missile trajectory are provided.

Memorandum presenting an investigation in the 27- by 27-inch preflight jet of the ejection release characteristics of the MB-1 rocket from the missile bay of a 0.04956-scaled model of the Convair F-106A. The MB-1 rocket was ejected with its fin tips retracted, for a simulated altitude of 18,670 feet at a Mach number of 1.59.