This report is a compilation of many of the pertinent research data acquired by the National Advisory Committee for Aeronautics on fuel performance in piston engines. The original data for this compilation are contained in many separate NACA reports which have in the present report been assembled in logical chapters that summarize the main conclusions of the various investigations. Complete details of each investigation are not included in this summary; however, such details may be found, in the original reports cited at the end of each chapter.

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A preliminary study has been made of a solid homogeneous reactor for stationary power plant application. The core consists of graphite spheres impregnated with uranium and thorium, and the coolant is bismuth. This concept possible offers advantages over other solid fuel reactor systems with respect to simplification of core structure, fuel fabrication and fuel handling, and reduction of fuel inventory external to the reactor. From the results of this preliminary study, it appears that the potential cost of electric power from this reactor is competitive with that from other reactor systems which have been proposed for the same application. The Po210 produced in the coolant presents a decontamination problem, but is also possibly a valuable by-producgt.

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The installation of crossheader pressure gauges on the reactors has shown that excessive pressure drops occur across some crossheader screen assemblies, and that the pressure drop across the four inch assemblies in the B, D, and F Reactors is significantly greater than the six inch assemblies at the DR and H Reactors. Since the inlet water system pressure is limited to the 4.5 psi discharge pressure of the secondary pumps, the reduction of pressure resistance downstream of that point would result in higher reactor flow rates and increased boiling limits. This test described in this report was initiated to determine if four inch crossheader screens having equal and 50% greater free-area than DR -- H screens would significantly reduce the crossheader screen pressure drops at the B, D, and F Reactors, and to obtain information regarding cone screen plugging rates with larger size screen openings.

About twenty-five to thirty per cent of the uranium slugs canned in the Metal Preparation Section do not meet specifications and are rejected. These rejected slugs are recovered by a chemical process and prepared for re-canning. The current recovery process consists essentially of a sodium hydroxide-sodium nitrate bath for chemically removing the aluminum can and the bonding medium, followed by hydrofluoric acid and nitric acid baths to remove the remaining compound layer and to pickle the slugs before they are returned to the process canning line. Recent studies have indicated the possibility of using a more economical means of recovery. this includes the mechanical removal of the aluminum can and most of the bonding medium, followed by a chemical removal of the residual compound layer by a solution of sodium hydroxide.

About twenty-five to thirty per cent of the uranium slugs canned in the Metal Preparation Section do not meet specifications and are rejected. These rejected slugs are recovered by a chemical process and prepared for re-canning. The canning operation provides a coating of metal composed principally of elemental aluminum and silicon with traces of copper and tin, which bonds the aluminum can to the slug. The elements in intimate contact with the slug combine chemically with the uranium to form the tenacious compound layer. The current recovery process consists essentially of a sodium hydroxide-sodium nitrate bath for chemically removing the aluminum can and the bonding medium, followed by hydrofluoric acid and nitric acid baths to remove the remaining compound layer and to pickle the slugs before they are returned to the process canning line. Recent studies have indicated the possibility of using a more economical means of recovery. This includes the mechanical removal of the aluminum can and most of the bonding medium, followed by a chemical removal of the residual compound layer by a solution of sodium hydroxide. A laboratory scale investigation was made to determine whether a solution of sodium hydroxide would remove the compound layer from de-canned, …

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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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Increased activities in Cryogenic Engineering have brought about the need for a compilation of available data. The purpose of the Cryogenic Data Book is to provide a condensed source of reliable data and reference information for those working in the cryogenic field. Specifically the data were compiled with a view toward the design of liquid hydrogen bubble chambers.

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.

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From abstract: "The circumstances are described pertaining to an explosion in a TNX evaporator during the concentration of a uranyl nitrate-nitric acid solution. TBP and Amsco diluent were probably present in the evaporator charge. A laboratory program involving small-scale atmospheric and closed-vessel distillations of various mixtures of UNH, HNO3, Amsco, TBP, and water indicate that an exothermic reaction between TBP and UNH, or between TBP and HNO3, or both, was responsible for the explosion. The danger areas of temperature, TBP concentration, pressure, and heating rate are defined and recommendations are made for safe evaporator operation.

Report discussing testing of a model of the McDonnell F3H-2N to determine its pitch-up and buffet boundaries and its longitudinal stability and control data obtainable with the pulse-tail technique. Stability was found to be less at low trim angles of attack than at high trim angles of attack up to a point. The buffet boundary was not obtainable through this testing.

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As recommended in a previous report a study of the NO₂ and HNO₃ exposures of plant personnel in the 224 U Building has been made. Concentrations of NO₂ and HNO₃ from the 224 U roof stack, in the concentrator cells, and in the calcining pot rooms have been determined. The problems have been outlined and recommendations have been made for its alleviation.

The compound RbU/sub 6/F/sub 25/ has a hexagonal crystal structure with the parameters a/sub o/ = 8.195 plus or minus 0.002 A and c/sub o/ = 16.437 plus or minus 0.002 A. This compound is believed to be isomorphous to KU/sub 6/F/sub 25/ and KTh/sub 6/F/sub 25/. (auth) uranium hexafluoride -chlorine trifluoride -hydrogen fluoride from a knowledge of the behavior of the three binary systems. The conditions under which chlorine trifluoride and hydrogen fluoride could be removed from uranium hexafluoride by fractional distillation are discussed. (auth)

From Summary: "An approximate analysis of the nonlinear effects of initial twist and large deflections on the torsional stiffness of a cantilever plate subjected to a nonuniform temperature distribution is presented. The Von Karman large-deflection equations are satisfied through the use of a variational principle. The results show that initial twist and applied moments can have significant effects on the changes in stiffness produced by nonuniform heating, particularly in the region of the buckling temperature difference. Results calculated by this approximate analysis are in satisfactory agreement with measured torsional deformations and changes in natural frequency."

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The geology of the Hanford-White Bluffs area was studied preliminary to drilling well(s) and developing an underground water supply. A study of the geology of the Hanford-White Bluffs area has shown that it consists of terrace deposits of sand and gravel covering a consolidated sandstone known as the Ringold formation. Beneath the Ringold are successive layers of basalt interbedded with volcanic ash, sand and other materials. In the past the Columbia River has cut channels through the area which extended downward into the Ringold formation. The old channels have been filled and upgraded to the present land surface in repeated flooding of the river over a long period of time. An aquifer used needed to be capable of supplying more than 34 million gallons of water per day.