The following report describes a gaseous scintillation counting system, including the production and operation of the counter.

The benefits of the poison spline system as developed and partially tested by the Facilities Engineering Operation are considered over a two year period. The full pile operational charge-discharge installation at the end of that time could make the poison spline system a marginal operation. This document list the production gains that are possible, how these gains compare with the cost of the poison spline system, and how this system compares with other available supplementary reactivity control systems.

Photoinduced electron spin resonance signals have been observed in isolated chloroplasts and other green materials with a growth time not affected by reducing the temperature to -140 deg. This is interpreted in terms of conduction-band and trapped-electron theory.

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Abstract: This report presents the results of plant optimization studies and cost estimates of the reference design for a natural uranium, graphite moderated, gas-cooled reactor and power plant which was described in NAA-SR-1833.

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A method has been developed for the uniform coating of graphite tubes with carbides of niobium, tantalum, and zirconinm by thermal decomposition of their respective halide vapors. Conditions of coating temperature and pressure are so chosen as to prevent the deposition of metal, but to permit the formation of the carbide as rapidly as carbon can diffuse to the surface. If the carbon diffusion can be made the rate-limiting step, the coating process becomes self- regulating and uniform thickness results. The limits of the temperature-pressure range have been determined experimentally for the thermal decomposition of zirconium iodide and of the chlorides and bromides of niobium, tantalum, and zirconium. With the successful development of coating equipment and definition of conditions, 99 blowpope test specimens were coated with uniform, continuous, and adherent layers of the carbides in three ranges of thickness, light (0.001 in.), medium (0.005 in.), and heavy (0.01 in.). Determinatlons were made of the coefficient for the diffusion of carbon in zirconium carbide as a function of temperature. Exploratory work on small specimens of graphite impregnated with 7 wt.% uranium indicated that the coating results were essentially unchanged, but that loss of uranium occurred. Means of avoiding the loss of …

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BSR Loading 33 consists of an essentially 5 by 6 fuel element array completely reflected by water. It was controlled by means of two boron carbide shim-safety rods and a type 347 stainless steel regulating rod with an 57-mil wall, located as shown in Fig. a. The critical mass was about 3.4 kg of U/sup 235/ , with an excess reactivity for the clean cold loading of about 0.6%. The total mass in the initial loading was 3.6 kg of U/sup 235/. Loading 33 was initially assembled in November 1954, from clean cold fuel elements. The power calibration was made during the first series of runs at power levels appreciably above 1 watt. Cobalt foils were used as the detector material for the thermal neutron flux determination in the lattice. The foils were exposed at 6-in. intervals in vertical traverses in the water passage between the last two plates on the outside of the fuel elements. Measurements were also mnde along the vertical axis of the element in lattice position 25, which was approximately at the center of the configuration. Cadmium ratios were determined at centerline and at 6in. intervals below centerline. Symmetrical flux distribution was assumed around the north-south …

Memorandum presenting two right circular cylinders tested in axial free flight over a Mach number range of 0.4 to 1.7 by using the rocket-boosted-model technique. Results regarding time history, basic data cross plots, center of pressure, and drag are provided.

Report presenting a brief evaluation of pentaborane-JP-4 fuel mixtures in a turbojet engine at a simulated flight altitude of 50,000 feet and a Mach number of 0.8. Engine data included thrust and specific fuel consumption is provided in tabular and graphical form for various fuel blends as well as photographs of the condition of the engine at the end of the investigation.

From Introduction: "The data presented herein include the standard engine performance parameters of net thrust, specific fuel consumption, and engine total-pressure ratio that reflect the performance available from the use of pentaborane as a fuel. The influence of the boric oxide deposits from the high-concentration pentaborane fuels on engine component performance is presented."

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Lecture presented at the Atomic Industrial Forum's Third Course on Reactor Materials, Stanford University, Stanford, California, July 9-19, 1957A review of progress in the use of liquid metals is presented. A number of liquid metals are compared, and the general problems of selecting container materials are considered. In addition. a discussion of corrosion mechanisms and corrosion testing methods commonly employed are examined as well as problems encountered with the liquid metals of greatest interest. (J.R.D.)

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Laboratory scale experiments with synthetic Purex 1WW and HAW have demonstrated the feasibility of recovering cesium by precipitation with metal ferrocyanides and ferricyanides. One method for recovery of cesium involves neutralization of the precipitate ferric hydroxide and sodium diuranate, and recovery of cesium from the supernate by precipitation with zinc ferrocyanide. Another method involves precipitation with nickel or ferric ferrocyanide from partially neutralized 1WW, or from HAW. The second method yields a voluminous precipitate with low specific activity and poor radiochemical purity of the cesium, thus necessitating further purification and concentration of cesium before packaging. This can be accomplished by metathesis of the precipitate with sodium hydroxide and precipitation of cesium with zinc ferrocyanide. Other methods for recovery the cesium from metal ferrocyanides have been investigated by other workers. Several of the more attractive cesium recovery flowsheets have been demonstrated with synthetic solutions on the laboratory scale. To demonstrate the feasibility of cesium recovery from plant solutions, the effects of radiation and trace chemicals (such as corrosion products, fission products, and impurities in uranium and process reagents) must be determined. Therefore, the present work was performed with full-level Purex waste solutions, both 1WW and HAW.

This report is a bibliography divided into two sections: one that documents books and journal articles, the other containing classified and unclassified documents, that are based around gaseous detonation. These sources cover the period between 1941 to October of 1957.

Abstract: "The energy gained by a deuterium plasma, from a three megacycle per second radiofrequency field, was studied experimentally. A static magnetic field, in the form of a "mirror", was used. The coil of an rf resonant circuit, placed at the center of the machine produced a time-varying magnetic field parallel to the static field. This, in turn, induced an electrical field, in an azmuthal direction, which acted on the ions. When this was in synchronism with the cyclotron frequency, the ions could pick up energy. At this resonance the light intensity from the plasma increased markedly. This effect was used as evidence for the transfer of energy to the ions."

Report discussing a study aimed at pinpointing the cause of banding segregation in arc-melted uranium-niobium alloys and suggesting possible methods for eliminating banding.

This report concerns the continuing problem of providing waste tank designs which will insure safe storage of radioactive waste over long periods of time. These tanks must withstand severe stresses imposed by earth loading, by hydrostatic pressure and by temperature gradients. The temperature gradients are caused by contained in the waste. The waste entering the tank is relatively cold, but the temperature rises rather rapidly to the boiling point as filling proceeds and then the temperature continues to rise as self-concentration increases the boiling point of the waste. The temperature gradients are therefore transient in character and they may be calculated only by rather tedious and complex methods; however, the gradients must be established in order to provide design data for structural design purposes. This report describes the methods used to calculate the temperature gradients and presents the calculated results for a particular tank design used under various operating conditions.

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