The purpose of the investigation was to locate new uranium ore deposits and sites which are favorable for exploration drilling.

Memorandum presenting an investigation conducted with an NACA submerged inlet at Mach numbers from 1.17 to 1.99. Total-pressure ratio, mass-flow ratio, and static pressure distribution along the ramp and main body were obtained at angles of attack of 0 and 6 degrees for a side inlet location. The results showed that the maximum total-pressure ratio attainable with the submerged inlet decreased from 0.83 at a Mach number of 1.17 to 0.52 at a Mach number of 1.99.

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.

Memorandum presenting an investigation of the rolling effectiveness of a partial-span, perforated spoiler on a wing with 45 degrees of sweepback at Mach numbers from 0.25 to 0.96. The effects of the spoiler on the lift, drag, and pitching moment were also determined. Results regarding Reynolds number, Mach number, and predicted rate of roll are provided.

"This report covers mainly the work completed since the last interim report, HNL Log No. 0-4714. This report includes results from studies of the rare earth distribution in bismuth-uranium and fused chloride and studies of fused chloride behavior."

Report presenting an investigation in the transonic tunnel on the effect of sweepback angle on the wing-body characteristics at a range of Mach numbers. Results regarding lift characteristics, drag characteristics, and pitching-moment characteristics are provided.

Report discussing an investigation using rocket-propelled vehicles in free flight to determine the effect of fuselage-diameter - wing-span ratio on the damping-in-roll characteristics of delta wings at a range of Mach numbers. The damping-in-roll derivative was found to decrease when the fuselage-diameter - wing-span ratio was increased. The experimental results are compared to calculated values.

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This quarterly report details activities in analytical research by the Applied Research Unit of the Nucleonics Division during the months of April, May, and June 1952.

The work reported here is a continuation of that reported in UCRL-1962. Approximate breakdown voltages and spark damage estimates have been made for the metals Ag, Ti, Aluminum Alloy 52-SO, Stainless Steel 316 and various combinations of Inconel and Cu.

Abstract: "The purpose of the investigation was to study the effects of gamma radiation from a cobalt-60 source on the physical properties and halogen evolution from the plastics polyvinyl chloride and polymonochlorotrifluoroethylene. Samples exposed for 2 to 28 days to a source of approximately 25,000 Roentgens per minute showed an appreciable evolution of both fluorine and chlorine. Tests on polymonochlorotrifluoroethylene for tensile, impact, and shear strength showed rapidly decreasing values as the radiation exposure was increased. Similar physical tests on exposed polyvinyl chloride showed increased impact and shear strengths and a lower tensile strength."

Abstract: "A quantitative method for the determination of individual rare earths in thorium down to a level of 0.05 ppm, is described. The procedure consists of a chromatographic cellulose-columns separation followed by a solution-type spectrographic determination. Values are given for the recovery of a number of rare earths using this combined procedure."

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From to the files: To date, all the mineralization seen in the Monument Valley area in the Shinarump formation has been in scour channels. The mineralized rock occurs at or near the bottom of the channel. On Hoskinnini Mesa, all the channels examined to date contain some mineralized material. Channels observed may in some cases contain copper without apparent uranium mineralization; others definitely exhibit copper-uranium mineralization.

The following report describes the process to determine the method for determination of americium in the presence of plutonium and uranium.

It is considered appropriate occasionally to make independent checks on the effectiveness of the plant laundry in removing radioactive contamination from plant-issue protective clothing. Previous surveys have offered constructive criticism resulting in improved handling of high level and soft beta contaminated clothing and incorporation in new designs of ventilating and air sampling recommendations. Recurrently the adequacy of laundry reject limits is questioned, and only recently an accurate, special study resulted in relaxed limits for Metal Preparation area clothing. A current question concerns the advisability of determining the reject level on the beta-gamma monitor more frequently than once a day. 2 tabs.

Report presenting an investigation of a sweptback wing in combination with a fuselage of a type considered suitable for long-range, high-speed airplanes in the 12-foot pressure wind tunnel. The investigations included tests of the wing alone, the wing-fuselage combination, and the effects of fences.

A procedure for calculating three-dimensional steady and nonsteady supersonic flows with the method of characteristics is developed and discussed. An approximate method is deduced from the characteristics method and shown to be of practical value at high supersonic speeds.

Report presenting an investigation to determine the characteristics of a double-shroud cooling-air ejector. The performance of a single-shroud ejector with a clamshell-type variable-area actuating nozzle was compared with that of an ejector having a conical nozzle. Results regarding the mechanics of ejector flow systems, effect of variable-area primary nozzle on ejector performance, double-shroud-ejector performance, and application of data are provided.

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Periodic solids purges of reactor process tubes are necessary to remove the film deposition on slugs and tubes. This film is undesirable for it constricts the water annulus, and thereby reduces the flow of cooling water and impedes the transfer of heat from slugs to the water. Prior to February, 1951, purging was accomplished only while the reactor was in a non-operating status. Subsequently, the feasibility of successful film removal during operation has been demonstrated in accordance with the provisions of Production Test 105-417-P, ``Process Tube Purges During Reactor Operation.`` This document reviews, in the light of additional purging experience, the initial test results, which are recorded in HW-20717 and subsequent purging experience to consider the desirability of adopting the use of this purging technique as a standard practice when reactor power levels are restricted by excessive film formation in the process tubes.