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.

Bismuth analytical methods were investigated for the purpose of selecting procedures which are satisfactory for the analysis of solutions containing plutonium and bismuth. The gravimetric procedure which is recommended for samples containing these two elements includes removal of the plutonium by peroxide precipitation, separation of the bismuth by precipitation with sodium carbonate, and final ignition of the bismuth as a phosphate. Necessary equipment and experimental technique are described. In the analysis of eight known samples by the recommended method, the average recovery of bismuth was 99.76 percent, with a standard deviation of 0.22 percent. The known samples contained about 35 mg of bismuth and 25 mg of plutonium. For similar samples in routine work, the confidence limits at the 95 percent level for the average of triplicated determinations are +- 0.30 percent of the bismuth in the the sample. Other methods investigated and having possible application for some Pu-Bi analysis problems include electrodeposition of bismuth on a mercury cathode and gravimetric analysis with BiCr(CNS)6 as the weighed product.

Determination of cadmium in plutonium-cadmium solutions was successfully accomplished by separating the plutonium as an insoluble peroxide, evaporating the solution containing the cadmium, and weighing the latter as a sulfate. with 5 t0 20 mg of cadmium and similar amounts of plutonium, the 95% confidence limits for the average of triplicate determinations was to be +- 0.3 percent of the cadmium in the sample. When samples contained as little as 5 mg of cadmium, it was necessary to correct the weight of cadmium sulfate with a carefully determined reagent blank which originated mainly from the action of hydrogen peroxide on glass containers.

Tests were conducted on a laboratory and semi-plant scale to determine the effect of permitting scrap grossly contaminated with uranium to be used in steel manufacture. It was found the most of the uranium is removed with the slag. Steel made with this scrap would have a uranium constituent so little above that made with uncontaminated scrap as to be hardly significant. The slag itself would not present any hazard in handling or normal use. It is recommended, therefore, that in the future steel with only surface uranium contamination be released through normal scrap channels.

A search for gamma-ray activities with period 1-100 msec from thermal neutron fission of U235 gave negative results. 0.43 +- 0.03 sec was the shortest observed. The period of B12 was found to be 27 +- 3 msec. The cyclotron beam was pulsed to supply 1-10 msec neutron bursts. coincidence scintillation deters were employed.

Report presenting an investigation of the hydrodynamic characteristics of a model of a 130,000-pound transonic flying-boat design with a high length-beam ratio planing-tail hull, sweptback gull wings with wing-tip floats, and wing-root jet-power-plant installation. Results regarding the aerodynamic, hydrostatic, and hydrodynamic qualities are provided.

The relative physiological and toxicological properties of americium and plutonium have been studied following their intravenous administration to rats. The urinary and fecal excretion of americium was similar to that of plutonium administered as Pu(N0{sub 3}){sub 4}. The deposition of americium the tissues and organs of the rat was also similar to that observed for plutonium. The liver and the skeleton were the major sites of deposition. Zirconium citrate administered 15 minutes after injection of americium increased the urinary excretion of americium and decreased the amount found in the liver and the skeleton at 4 and 16 days. LD{sub 30}{sup 50} studies showed americium was slightly less toxic when given in the acute toxic range than was plutonium. The difference was, however, too slight to be important in establishing a larger tolerance does for americium. Survival studies, hematological observations, bone marrow observations, comparison of tumor incidence and the incidence of skeletal abnormalities indicated that americium and plutonium have essentially the same chronic toxicity when given on an equal {mu}c. basis. These studies support the conclusion that the tolerance values for americium should be essentially the same as those for Plutonium.

A report about metallurgy, chemistry, and physics of metals and alloys. Particular metals include zirconium, thorium, and vanadium metal as well as other earth metals.

Report summarizing work done by the Ames Laboratory from April, 1951 through June, 1951 in the fields of metallurgy, chemistry, physics, and engineering.

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Investigation of principles of pulse-column design and effects of operating variables.

Report documenting the suitability of Indiana for plant locations to produce synthetic liquid fuels, based on raw materials such as oil shale, natural gas, and coal.

Report documenting the suitability of North Carolina for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.

Report documenting the suitability of Oklahoma for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.

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Memorandum presenting a description of a method of telemetering skin temperature using a small resistance wire pickup with a time constant of less than 0.003 second to determine boundary-layer heat-transfer coefficients. An evaluation of the accuracy of the method of measuring the heat-transfer coefficient is given for a particular application.

Report presenting the use of Theodorsen's propeller theory to calculate the performance of a dual-rotating propeller with nonideal load distributions. Results regarding the propeller characteristics were made for several blade-angle settings and flight Mach numbers.

Slag and crucible can be dissolved satisfactorily by the Los Alamos method of total dissolution with nitric acid in the presence of aluminum nitrate. Extraction of 99% of the plutonium from total dissolution salted with aluminum nitrate was achieved by three successive contactings with 1/10 volumes of 30% TBp- AMSCO 125-90W. The TBPAMSCO phases contacted with leaching solutions salted with calcium nitrate must be scrubbed to remove calcium. Stripping with three 1/10 volumes of 0.1M hydroxylamine sulfate removes 99% of the plutonium from the 30% TBPAMSCO, initially O.lM HNO/sub 3/. Plutonium(III) oxalate, (which could be blended into 234-5 operations) can be precipitated from the aqueous strip solution. It is chemically feasible to recycle slag and crucible solution to the Redox IIA column in amounts up to at least lO% of IIAF by volume. It is also chemically feasible to recycle nitric acid solution of slag crucible obtained in the presence of aluminum nitrate to the Product Precipitation step of the Second Decontamination Cycle of the Bismuth Phosphate Process. (auth)

Report evaluating different methods of preparing nitric acid solution and different methods of separating plutonium from this nitric acid solution of slag and crucible. Methods are explained and experimental data is given.

Exponential rise times, T, of neutron flux in an Oy-Tu assembly have been measured for a set of points essentially equally spaced reactivity-wise in the interval between delayed and prompt critical corresponding to [infinity] > T > 5 seconds. The relationship between positive period and reactivity thus obtained is used to decide (preferentially) between two currently used but divergent collections of delayed neutron data, specifically with respect to the relative abundances of delayed neutrons in the different decay periods. Results of other reactivity measurements supplementing the positive period data are also given.

The purpose of the research work presented in this volume is to develop a process for the separation and purification of actinium-227 produced by neutron bombardment of radium-226 and to develop methods by which uniform films of actinium metal may be deposited on metallic surfaces. The design work on the cave structure and mechanical equipment used in the actinium separation is proceeding on schedule. As the mechanical design phase is nearing completion the emphasis is being directed toward processing equipment. The process as well as the mechanical equipment has been adapted from the research work of F. T. Hagemann and the Remote Control Group at Argonne National Laboratory. Consequently, one of the first objectives is to become familiary with the chemistry of the process and the operation of the mechanical equipment. Cold runs have been made on the T.T.A. benzene extraction using lanthanum and barium in place of actinium and radium. No difficulty with the operation was observed. The formation of precipitates was one of the difficulties encountered with the process as the precipitates carry radium. It has been found that metals such as nickel cause these precipitates to form and should, therefore, be avoided in the construction of equipment. …

The purpose of the research work reported in this volume is the development of a process for the separation and subsequent purification of radium from the K-65 (pitchblende) residue. Except for the accumulation of additional experimental data the process is essentially complete. After a preliminary extraction of about 85% of the lead and 40% of the silica with a 40% sodium hydroxide solution, the residue is treated with a solution containing both sodium hydroxide and sodium carbonate to obtain additional lead removal and partial conversion of the radium and barium sulfates to carbonates. After leaching out the soluble carbonates, the residue containing unconverted sulfates is treated with a sodium carbonate solution at 170{sup o} under pressure. A study of the amount and concentration of sodium carbonate required to obtain a satisfactory conversion of the sulfates has shown that the total sodium carbonate may be reduced by 40% and that smaller volumes of solution may be employed without serious decrease in the efficiency of the conversion. In order to make calculations on the number of steps and tank sizes for the radium-barium separation by fractional precipitation, equations have been developed to calculate this information from the theoretical separation factors determined experimentally. …

From introduction: "The prime motive behind the experiments described in this report and in those preceding it in this series is the desire to reduce the number of Redox cycles necessary for decontamination from fission products of the plutonium and uranium streams sufficient to allow final disposition of these two products...This report deals with the mechanics of manganese dioxide handing, laboratory development of manganese dioxide scavenging, and a series of experiments at multicurie level combining ruthenium volatilization and manganese dioxide scavenging in stainless steel equipment."