Report discussing a study to obtain a quantitative measurement of the movement and distribution of hydrogen among components such as magnesium metal chips, uranium tetrafluoride, and magnesium fluoride slag, similar to what would occur during a reaction in a thermite bomb.

Abstract: "The oxidation resistance of thin sheets of iron-28 w/o chromium-2.67 to 10.0 w/o alloys, nominally 0.004, 0.006, 0.008, 0.012, and 0.016 in. thick, was determined by exposure in static air for 100 hr at 2100 and 2300 F. A minimum of 3.67 and 9.37 w/o aluminum was necessary to prevent excessive oxidation of 0.004-in.-thick sheet material at 2100 and 2300 F, respectively. Correspondingly, specimens of lower aluminum content and greater thickness withstood the oxidation attack. Oxidation of iron-chromium-aluminum alloys appeared to be related to the diffusion of aluminum to surfaces of the sheet to form an adherent protective layer of Al2O3."

The following report presents neutron-flux measurements with the Mark I element, which include neutron-flux distribution and flux depression within the element.

Abstract: "In a study of the preparation and properties of delta-phase zirconium hydride it was found that large, sound bodies of the hydride can be prepared by direct combination of the elements if the rate of the reaction is retarded by limiting the supply of available hydrogen. Specimens up to 1-in. diameter were prepared using this technique. Because delta phase zirconium hydride does not readily form eutectics with iron-and nickel-base alloys below 1800 F these materials may be utilized for clodding the hydride. Delta-phase zirconium hydride is unaffected by exposure to liquid NaK or to nitrogen gas at temperatures below 1000 F. The hot hardness of delta-phase zirconium hydrid is about 130 kg per mm-2 at room temperature and 40 kg per mm-2 at 1500 F. The mean coefficient of thermal expansion (68 to 1337 F) is 6.5 x 10^-6 per deg F. The thermal conductivity varies from 5.7 Btu/(ft)(hr)(F) at 300 F to 5.1 Btu/(ft)(hr)(F) at 1300 F."

Abstract: A study has been made of the cladding of solid and powdered delta-phase zirconium hydride is both red and flat shapes with stainless steel. The program included investigations of metallurgical bonding, both with and without the sore of metallic barrier materials. Types 304 and 347 stainless steel were used for cladding material. The intermediate barrier-layer materials used were niobium, molybdenum, a combination of copper and molybdenum, and a combination of copper and niobium. The pressure-bonding techniques, involving the use of gas pressure at elevated temperatures, was employed in this study. Variable times and temperatures with a constant pressure of 10,000 poi were utilized by produce bonding. In this study, the best results were archived is cladding delta-phase zirconium hydride directly with Types 304 or 347 stainless steel. Good bonds were obtained by pressure bonding at 1600 F for 3 or 4 hr subsequent to pressure bonding at 1900 F for 1 to 2 hr at a pressure of 10,000 poi. Partial bonding was achieved between niobium and zirconium hydride and molybdeum and girconium hydride.

Abstract: A description is given of the design and operation of a windowed autoclave system employed in the study of corrosion by pressurized hot water. The device has been used to obtain time-lapse motion pictures of the swelling and rupture of deliberately defected zirconium-clad uranium specimens. A method is described by which corrosion rates were calculated from pressure and temperature measurements. A typical set of pictures taken during a test is presented, and corrosion rates are reported for uranium-0, 5, 10, 15, and 20 w/o zirconium alloys subjected subjected to 600 F water.

Abstract: The nonmetallic inclusions in both as-reduced and fabricated dingot uranium have been studied for comparison with those in ingot uranium. Special attention was paid to the hydride for the purpose of determining the amount and distribution in the various types of uranium. The types and distribution of other inclusions were also studied. It was found that the dingot uranium was of a higher quality than ingot uranium and was comparable to as-reduced derby uranium on the basis of over-all inclusion count. The hydrogen content in dingot uranium, however, was found to be appreciably higher than in either ingot or derby uranium.

Report discussing a study on casting techniques for the production of sound homogeneous extrusion blanks composed of aluminum-uranium alloys with 30 to 45 w/o uranium.

Abstract: "Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cost of UC, U2Tl, U3Si, or U6Ni dispersed in Zircology 2 and 30 volume per cent of UC or UN dispersed in Type 18-8 stainless steel have been investigated. Roll-clad plate-type elements of all these compositions may be fabricated by powder-metallurgy methods in such a manner that good core-to-cladding bonds and cores with uniform dispersions of discrete uranium-composed particles are obtained. From the standpoint of fabricability, elements containing UC is Zircology 2, UC in stainless steel, and UN in stainless steel are the most promising. The UN in stainless steel has the best corrosion resistance in 680 F degassed water; however, UC in stainless steel has the best resistance to corrosion in 700 F NaK."

The following report follows the procedures to compact blends of uranium tetrafluoride and magnesium, describing how lubrication of the compact effects the outcome of the blends.

The following report follows an experimental study that was made on the mass transport of chromium in polythermal inconel-fluoride fuel systems, followed by the technique of adding radioactive chromium-51 to the system as either CrF3 in the salt or as elemental chromium in the solid phase.

"This is a selective bibliography of books and periodical articles relating to extrusion die design with special emphasis on extrusion of beryllium. Material on the extrusion process has been included when it contains information that might be of possible help in die designing."

From abstract: "A detailed study is presented of some fundamental problems connected with the realization of a nuclear gaseous reactor rocket engine."

"This is a bibliography of journal articles relating to beryllium oxide. Sources consulted include; Chemical Abstracts, 1951-1955; Physics Abstracts, 1951-1955; Industrial Arts Index, 1955-Jan, 1957; and the library card catalog. Starred articles are available in the library.

Abstract: "This is a selective bibliography of books and periodical articles relating to die design of hot presses. Sources consulted include: ASM Review of Metal Literature, 1950-1954; Chemical Abstracts, 1950-1055; Engineering Index, 1950-1055; Industrial Arts Index, 1950-March 1957; Metallurgical Abstracts, 1950-1953; Nuclear Science Abstracts, 1950-March 1957; Physics Abstracts, 1950-1955; the library card catalog, and the Technical Information Division AEC card catalog."

This report describes the design, construction, and application of an electrical analogue for solution of the steady state problem. Teledeltos paper (an electrically conductive paper) was used to construct this analogue, and although this and other sheet materials has been used for heat transfer analogues in several previous investigations, it is believed that the present work is unique in the application of Teledeltos paper to three dimensional problems of radial symmetry.

Abstract: "Data on the isotopic degradation of heavy water used to deuterize deionizer beds at Savannah River Plant are presented. Also, the extent to which light hydrogen, chemically bound to aluminum surfaces may degrade heavy water is estimated."

Abstract: "A series of ternary additions of niobium, platinum, and molybdenum, of the order of 1.0 w/o and less, have been made to binary uranium - 0.5 w/o titanium, an alloy of some promise in the 7-heat-treated, water-quenched condition. Jominy bars of nine such alloys were tested, microstructurally examined, and hardness profiles obtained over their length. This paper deals with observations made for correlation of transformation behavior, microstructure, and hardness profiles over the spectrum of cooling rates experienced, directed toward the end of determining the effect of ternary additions in improving the properties of uranium."

This report follows studies that were made the quasi-stable pinch produced by a relatively long duration low voltage capacitor discharge (5ma, 5kv) in a 600 cm long, 15 cm diameter metal tube.

Abstract: "The problem of evaluating the method of sampling used on a particular uranium ore or concentrate is considered. It is pointed out that the purpose of this evaluation is to obtain data on possible biases of the sampling method, the way the sample is prepared for analysis, and the analysis itself. In addition, it is pointed out that some estimate of precision, either overall or individually, for each step is required. Examples of the use of the analysis of variance approach to these problems are given. Finally, some remarks are included on sampling problems associated with other materials used by the Food Materials Production Center."

From introduction: "One of the most important factors which must be considered in the chemical processing of spent fuel elements is the safe and economic disposal of gaseous radioactive fission product wastes given off in the fuel element dissolution operation. For this reason work is underway at ORNL to study the various gas disposal methods that might be used to handle the radioactive fission product gases, krypton, xenon, and iodine."

Abstract: A procedure is given for the concentration of gadolinium, dysprosium, and samarium in yttrium oxide by extraction of the thiocyanates with tributyl phosphate. Concentration of these elements up to 80-fold was obtained. Results are given on the effects of ammonium thiocynate and tributyl phosphate concentrations, as well as pH, temperature and sample size on the separation. Analyses of standard yttrium oxide samples after concentration of these rare earths are in good agreement with results obtained by direct spectrographic analyses.

The following report analyzes the scattering of neutrons by a rotating, deformed, even-even nucleus, providing two essential approximations and their justifications.

Abstract: "The percentage strain at which, or immediately higher than which, grain growth occurs on cold worked alpha recrystallize uranium sheet, appears to be at approximately 2-1/2 percent reduction in thickness. Grain growth from 20 microns to over 150 microns has been indicated for this region. This phenomena is especially noteworthy when deep drawn uranium shapes are to be reheated for a coining or restriking operation."