Report discussing performance estimates for several airplanes using General Electric AC-210 ramjet nuclear-powered engines. Assumptions used for designing the engines, radiation shield, and airframe are described. Potential tradeoffs in regards to power and weight reduction are also discussed.

An enriched I & E fuel element failed during irradiation under Production Test IP-109-AC in December, 1957. Radiometallurgical examination of this slug was requested by the IPD Process Analysis Operation. This report presents the results of the examination work.

The report is divided into: Fissionable materials (2000 program): studies related to production reactors, studies related to separations plants; reactor development (4000 program): Studies related to plutonium recycle program.

In the development of fuel elements for the NPR, one potentially serious fuel element problem -- high temperature uranium swelling -- has not been experimentally investigated. A series of experiments has been proposed in which uranium fuel rod with different amounts of Zircaloy-2 cladding will be irradiated to high exposure at temperatures equivalent to those expected in an NPR. These experiments should show the importance of high temperature uranium swelling as a limiting factor in NPR fuel element behavior. To obtain sample rod temperature of 250 to 300{degree}C on the surface and 500 to 650{degree}C at the center, the rods will be irradiated in aluminum capsules loaded in standard reactor process tubes. The high temperatures will be obtained by restricting the heat flow from the uranium sample to the coolant. The purpose of this test is to determine the validity of the heat transfer calculations used in predicting the temperature drops within the capsule by irradiating one capsule at known flux conditions and measuring the temperature attained by the uranium rod sample. The data obtained from this test will be used in determining the irradiation conditions required for the full scale uranium swelling tests.

The performance of I & E fuel elements under the original tests{sup 1} was such that they are now being charged at C Reactor on a production basis. Data obtained from the original test, however, were not sufficient to indicate long term corrosion effects of the use of these elements, nor to accurately define their operating characteristics. It is the intent of this test, therefore, to provide for long term corrosion monitoring in tubes charged with and without water-mixing pieces; and to obtain the required operating data to refine the operating characteristics of this fuel upon which power limits are based.

The use of organic cooling media for nuclear reactors operating at high power levels predicates the use of a coolant which will not react violently with metallic uranium in the event of a fuel element failure. This report describes the testing, and subsequent examination, of two pieces of irradiated uranium which were immersed in monoisopropylbiphenyl (MIPB) at high temperatures and pressures for periods of time up to twenty-five days. The uranium samples had different irradiation histories and cooling times. Similar experiments had been performed with unirradiated uranium by the Corrosion and Coatings Operation, and it was wished to determine whether irradiated uranium would react with MIPB in a different manner.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Constitutionality and Construction of Portions of the Adult Probation and Parole Law of 1957.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether a domestic or foreign corporation may qualify in Texas to act as the general agent of an insurance company other than a life insurance company.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Authority of the State Board of Control to modify and alter the permanent entrances into the Capitol grounds.

The purpose of this work has been to determine the production rate of tritium in fringe Li-Al alloy columns with the degree of precision necessary for economic analyses of such reactor loadings. These results are provided for use in such an analysis. This experiment indicates the production rate of tritium in the outermost fringe tubes to be T = 0.0216 M{sub E} = 0.175 M{sub t} where T = grams of tritium per full length (67 pieces) charge of Li-Al alloy material; M{sub E} = MWD/adjacent ton of E metal; M{sub t} = MWD/adjacent tube of E metal. The above values should apply for fringe loads utilizing greater or smaller quantities of E metal; that is, for isotope production loadings which are over or under-compensated from a reactivity standpoint. In the actual test load it was calculated that one gram of tritium and 13.5 grams of Pu were made for each 21.3 grams of U-235 burned up. During the same time interval the displaced uranium loading would have generated 24.3 grams of Pu and burned up 29.9 grams of U-235. The factor which seems to limit the accuracy with which these data can be interpreted is the ratio of the …

"The object of this note is to outline an Omnitron source scheme where the sheath voltage of the Omnitron is not carried over into the reactor region."

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Following HRT runs 13 and 14, several metallic specimens were removed from the high pressure system and transferred to the Materials Section for examination. Samples of scale accumulation in the high pressure system were also taken after these runs and transferred to the Materials Section. Examination and analyses of these several specimens are still in progress, but some of the results are available and are reported. A possible interpretation of some of these results indicates that a considerable quantity of nickel was contained in the core scale accumulation at the end of run 13, and that part of this nicke1 was dissolved in solution during run 14. The amount of nickel which may have come from this source during run 14 roughly accounts for all of the increase in nickel in solution durirg run 14. A significant amount of uranium was also found in the sca1e accunnulation in the core after run 13. (auth)

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Fabrication techniques for making metal-ceramic fuel elements containing 80 to 90 vol. f UN or UO/sub 2/ in a Type 302B stainless steel matrix were investigated. A hot press-forging procedure was most successful for of theoretical or better. This procedure consisted of sealing the cold-p;ressed core compacts in stainless steel picuture-frame packs, heating to 1900 deg F, and pressing to a total reduction in thickness of 35%. A pressure approximately 50 tsi was used specimens produced by this method were evaluated on the basis of their microstructure, modulas of rupture, electrical conduuctivity, and resistance to thermal shock. Microscopic and macrcscopic examination showed the presence of a continuous metal skeleton even in specimens containing 90 vol. a fuel. The modulus cf rupture at rcom amperature varied from 22,500 psi for a specimen containing; 63 vol. % UO/sub 2/ to 9,200 psi for a specimen containing 87 vol.% UO/sub 2/. Both the electrical conductivity and resistance to thermal shock of UO/sub 2/ were improved by the addition of a small volume of metal. Gaspressure-bonding techniques appear promising for cladding these cores into composite elements. (auth)

A search of the classified and unclassified literature concerning the degradation of a tributyl phosphate (TBP)-kerosene solvent has been conducted. Chemical Abstracts, Nuclesr Science Abstracts, Abstracts of Classified Reports, and the card file of the National Lead Company of Ohio's Library were included in the search. Pertinent information is presented, in abstract form, as it applies to extractant (TBP) degradation, diluent (kerosene) degradation, and solvent clean-up techniques. (auth)

Under the Atoms-For-Peace Plan, the specification that uranium be limited to 20% enrichment in the U/sup 236/ isotope has necessitated development of a highly-concentrated uranium--aluminum alloy as the fuel material in the composite aluminum plates of research reactor fuel elements. Efforts have been directed to determining the suitability of a nominal 48 wt.% U--Al alloy in relation to previously established procedures for manufacturing platetype aluminum fuel elements. Increasing the uranium concentration from 18 wt. % to the 48 wt.% resulted in increased segregation, higher strength, and loss of ductility, creating additional fabrication difficulties. Nonuniform deformation of the alloy during roll bonding into composite plates caused localized thinning of the cladding which may limit the material to specific reactor applications. Substitution of Type 6061 aluminum for Type 1100 alumium as frame and cladding of the fuel plates improves this condition. A fuel element, containing the 48 wt.% U-Al alloy, was irradiated in the active lattice of the MTR to an estimated burnup of 25% of the U/sup 235/ atoms with no observable damage. (auth)

For the centrifugal pump under investigation, the static head at pump suction, in feet absolute, at cavitation inception was correlated for water and for 1500 F NaK on the basis of the differences of the vapor pressures of the two liquids. The difference between the vapor pressure of water and NaK, for the same conditions of pump speed and liquid flow, was added to the water-test cavitation inception value, and this estimate proved to be a good approximation to the experimental value found for cavitation inception with NaK. (auth)

Memorandum presenting seven injectors of four different types that were tested for use with JP-4-oxygen-fluorine propellant combinations. By using the best of the injectors, high characteristic velocities were obtained over the complete range of 0- to 70-percent fluorine in the oxidant. Results regarding injector performance, heat rejection, injector with triplet-jet elements in skewed array, and fluorine addition are provided.

Report discussing various features of the stability of ballistic reentry shapes, including considerations for ballistic-missile and manned-satellite reentry capsules. Attainment of satisfactory stability of reentry bodies with subsonic terminal velocities was not found to be too difficult, but undesirable features that may cause marginal stability characteristics may be introduced in an effort to minimize weight. Reentry bodies with supersonic terminal velocities have fewer stability issues.

Report presenting the tracking performance of an automatically controlled interceptor in which the deflection channel incorporated a bank-angle-error computer that commanded rolling velocities of the interceptor proportional to the computed bank-angle errors. Results regarding gravity terms included in bank-angle-error computation and a comparison of modified system using bank-angle-error computer with the prototype system are provided.

From Introduction: "The importance of blunt noses as a means of reducing the heat transfer to high velocity missiles has recently received much publicity. The question of just what blunt shape is best is still moot, and it is the purpose of this paper to present and examine some recent experimental results which may throw some light on this problem."

Memorandum presenting net jet thrusts for stoichiometric hydrocarbon-air, hydrogen-air and pentaborane-air mixtures for equilibrium and frozen expansion in the exhaust nozzle at flight Mach numbers up to 10. Net jet thrusts for equilibrium flow were three to five times that for frozen flow at Mach 10 for the three fuels cited, a hydrocarbon, hydrogen, and pentaborane. Results regarding dissociation energies, reaction rate, residence time, and estimated minimum performance are provided.

Report presenting an investigation conducted on a full-scale afterburner and turbojet engine to determine the effect of pressure level on afterburner-wall temperature. For a given ratio of cooling airflow to afterburner gas flow, the afterburner-wall temperature increased as afterburner-outlet pressure was increased. The results indicated that heat transfer by luminous radiation was not significant any pressure level investigated.