Enriched U-Zr power tubes with various component sleeves, seals, and plates were evaluated for testing in the General Electric Test Reactor. The evaluation data are tabulated. (J. R. D.)

The feasibility of using the KEWB reactor as a pulsed neutron radiation source for use in studies of fuel element transient heating was studied. UC fuel rod samples were heated in the reactor. It was found that flux distribution in fuel samples could be mapped and thermal conductivity measurements for UC could be made by using fast response thermocouples distributed radially in the sample. (J. R.D.)

Tests were conducted to determine the amount of error introduced in reactor power data by radiation-induced voltages in cables and electrometer preamplifier chassis. The results, obtained near the central exposure facility of the KEWB (Reacter Safety Experiments), showed no observable radiation effects under the conditions of present use. Cable insulation resistance was measured during the radiation bursts. (C.J.G.)

The reaction of U0/sub 2/F/sub 2/ with hydrogen at 700 to 850 deg C was briefly investigated since it could constitute a major step in the recycle of U0/ sub 2/F/sub 2/ in the Fluorox process. The reaction in this temperature range proceeds according to the equation U0/sub 2/F/sub 2/ + H/sub 2/ yields U0/sub 2/ + 2 HF. Rates of the chemical reaction were not obtsined, since, with the thermogravimetric technique used, the rate-controlling process was bed diffusion. However, there is no doubt that the rate of chemical reaction is sufficiently high for the desired application. No significant amount of UF/sub 4/ was formed by the back-reaction, U0/sub 2/ + 4 HF yields UF/sub 4/ + 2 H/sub 2/0. (auth)

Chlorine may be determined in polyurethane by gravimetric or spectrophotometric techniques. The sample is burned in a special combustion tube with two oxygen inlets, the products of combustion are absorbed in a solution containing sodium hydroxide and hydrogen peroxide, and the chlorine is measured either gravimetrically as silver chloride or spectrophotometrically using mercuric thiocyanate and ferric perchlorate. Eighteen determinations of cblorine in known solutions of sodium chloroacetate or perchloric acid gave an average recovery of 98.3% with a standard deviation of 2.8%. (auth)

The effect of temperature and testing speed on the tension and compression properties of unalloyed plutouium was studied in the alpha , beta , gamma , and delta phases. Compressive formability data were obtained for a load of 100,000 lbs in the aforementioned phases. In addition, preliminary creep, tension impact, and torsion data for alpha -phase plutonium are reported. Extrusion constants and pressures for the beta , gamma , and delta phases were obtained. The roomtemperature tension and compression properties of the beta - and #gg-extruded plutonium were determined. Metallo graphic studies were made to determine the effect of tension, compression, and extrusion, in the indicated phases, on the microstructure of as-cast plutonium. (auth)

jectives, the accomplishments, and a summary of the work outstanding. The obtectives of the experimental and analytical studies were to investigate and reach an understanding of the kinetic behavior of aqueous homogeneous reactors. Information produced by the program, experiments on the spherical core, capsule experiments, and the remaining work schedule are discussed. (W.D.M.)

Activities at the Michigan Reactor and pneumatic tube system are outlined. Various modifications including installation and operation of a "bunny" rabbit pneumatic tube system for transferring samples from laboratory to counter are described. Prelimirary investigation for design of a neutron generator for activation work is described. Modifications to the 100-channel pulse-height analyzer including addition of auxillary circuits and additioral detectors are sumnnarized. In nuclear chemistry a cyclotron bombardment to produce long-lived vanadium tracer for yield determinations in activation analysis is described. Summaries of project work which have been published on absolute (d, alpha) reaction cross sections and excitation functions, use of computers in nuclear data analysis, and research on Ir/sup 196/ are presented. Study of the gamma spectra of 33-second Kr/sup 90/, 41-second Xe/sup 139/, and some longer-lived fission product rare gases is reported and a summary of preliminary results is given. Detection of a long-lived isomer of Ag/sup 108/ in old Ag/sup 110m/ samples is reported and new values for the branching ratios of 2.4minute Ag/sup 108/ are given. Activities of the Subcommittee on Radiochemistry are summarized. Development of a radiochemical procedure by the use of amalgam exchange is reported and exchange of the elements Cd, Tl, Zn, Pb, …

>The importance of prevention of fires and explosions involving uranium, zircomum, plutonium, and thorium, which are of particular interest to the nuclear energy program, made imperative the study of their ignition behavior and oxidation kinetics. Methods of measurements of ignition characteristics of uranium and zirconium were developed and used to determine the effects of variables, such as surface preparation, metallurgical history, specific area (sample size), additives to the metal, and oxygen content and presence of moisture in the oxidizing gas. The study of ignition characteristics was supported by study of the effects of similar variables on the kinetics of oxidation of uranium and zirconium and binary alloys of each. The oxidation of uranium always proceeded in two linear stages over the temperature range of 125 to 295 deg C at pressures of 20, 50, 200, and 800 mm of oxygen. The temperature dependences of both stages indicate an activation energy dependent on pressure. The presence of ten additive elements in uranium metal caused only very small effects on the oxidation. The oxidation of zirconium was independent of pressure and proceeded according to a cubic rate law over the temperature range from 400 to 900 deg C, with an activation energy …

Tables of neutron total, elastic, inelastic, scattering, and absorption cross sections are presented for the elements V through Sn at 0.001 to 14.5 Mev. (C.J.G.)

Tables of neutron total, elastic, inelastic, scattering, and absorption cross sections are presented for the elements hydrogen through titanium at 0.001 to 14.5 Mev. (C.J.G.)

Absorption spectrophotometric methods were used in a study of complex ion formation and acid-base reactions in fused chloride and nitrate systems. Several methods for the treatment of spectrophotometric data were investigated. The spectra of various chromium salts were determined in three nitrate melts and in fused lithium chloride-pothssium chloride. In low solute concentrations in LiNO/sub 3/-KNO/sub 3/, NaNC/sub 3/-KNO/sub 3/, and LiCl-KCl melts, the species found was the chromate ion, while in molten AgNO/sub 3/, the species found was the dichromate ion. An explanation of these observations is put forward, and their significance discussed. Formation constants for leadchloro and lead-bromo complexes were evaluated. The values obtained for the first two lead-chloro and leadbromo complexes are 11.3, 3.6 and 13.3 and 6.0, respectively. Mass spectral studies of the gaseous products of the reaction between dichromate ion and nitrate ion in fused NaNO/sub 3/-KNO/sub 3/ showed that the reaction is of an acidbase type, involving formation of a nitronium ion which then reacts with nitrate ion to evolve dinitrogen pentoxide decomposition products. A number of qualitative experiments in fused salts involving acid-base reactions were performed, and their relation to oxidation-reduction processes in the fused salts is discussed. An analogy is drawn to …

The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO/sub 2/ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr. (auth)

Tests are described to determine the amount of entrained moisture occurring in the steam of the Pathfinder Power Plant as design parameters were varied. It was found that the height of the moisture separator and the velocity of the steam should be adjusted so that the permissible steam velocity for the particular height is not exceeded. If this is done, the amount of moisture entering the separator should be less than 1%, an amount of moisture that should not be difficult to remove with moisture separators. (J.R.D.)

Submitted as a thesis by William Berdell Barlage, Jr. Heat transfer studies were refined and extended to the point where the results could be generalized into a mathematical correlation valid over a reasonably wide range of variables. An extended study was made of the rate of heat transfer between benzene and water in direct contact in a pulse column, and of the operating variables which controlled the behavior. In this mode of heat transfer the benzene was dispersed as a family of droplets into the water, which formed the continuous phase. The pulse column was 1.92-in. in inside diam., and contained 8 stainless steel perforated plates spaced 2.00 inches apart. The plates were perforated with 1/8-in. holes in a triangular 60 deg pattern, providing 24.6 per cent free area. The equipment was carefully insulated and modified in many details in order to permit precise heat transfer measurements. The operating conditions were varied so as to provide wide ranges of variables and heat transfer responses. (W.L.H.)

None

A set of equations was written which allowed the calculation of equilibrium concentrations in the solvent phase of nitric acid and uranyl nitrate, given the initial TBP concentration in the solvent and the aqueous phase concentrations of acid and uranium. An ORACLE subroutine was written based on these equations which will calculate a set of equilibrium values in about 35 milliseconds. The subroutine was incorporated into a short program to calculate equilibrium points. A set of calculated points are presented in graphical form for 5, up to 7 M and uranyl nitrate concentrations up to 0.6 M in the aqueous phase. Since these calculations were based on limited data, it is the purpose of this memo to invite comment on their accuracy. The equations were reworked from a Russian paper by A. M. Rozen and L. P. Khorkhorina, using emperical polynomial fits for some poorly defined parameters, and were based principally on data from J. W. Codding. This project was undertaken to provide a subroutine to calculate equilibria in a general purpose ORACLE program to calculate the performance of multi-stage compound extraction cascades with more than one significant solute. (auth)

An occurrence at the SRE which caused approximately 7 fuel elements to part when being pulled from the reactor complicated reprocessing, however the bulk of the elements may still be reprocessed as planned. New or reworked pants for the mechanical decladder were supplied by the fabricators for rebuilding in ORNL shops. Administrative actions dictated by budgetary considerations include reduction of UO/sub 2/ pellet order to the quantity needed this fiscal year, reduction of Mark III prototype fuel element to 12, stoppage of all work by REE Division personnel, and stoppage of all work not related to SRE fuel element reprocessing. (auth)

The unclassified literature covering 2498 reports from 1907 through 1957 has been searched for isotopic exchange and isotepic separation reactions involving U and the lighter elements of the periodic chart through atomic number 30. From 1953 to 1957, all elements were included Numerous references to isotope properties, isotopic ratios, and kinetic isotope effects were included. This is a complete revision of TID-3036 (Revised) issued June 4, 1954. An author index is included. (auth)

Methods are presented for the analysis of 41 refractory materials. An evaluation of the accuracy and the precision of these techniques are also given The materials studied are the borides of hafnium, molybdenum, niobiumL rhenium, tantalum, thorium, titanium, tungsten, uranium vanadium, and zirconium; the carbides of hafnium molybdenum, miobium, silicon, tantalum, thorium, titanium, tungsten, uranium, vanadium, and zircomium; the nitrides of boron, hafnium, niobium, silicon, tantalum, titanium, uranium, and zirconium; the silicides of molybdenum, rhenium, tantalum, titanium, tungsten, vanadium, and zirconium; and mixed carbides of uranium with hafnium, niobium, tantalum, or zirconium. (auth)

At the present time, plants in the 100 to 500 Mw size range are more numerous and carry the greatest portion (over 50%) of the total steam-electric plant load in the US utillties industry. The contribution of plants of over 1,000-Mw capacity is increasing more rapidly than any other size classification and at present represents about 10% of the total capacity. By 1962 the TVA will have six plants with capacities of over 1,000-Mw. The largest steam-electric plant in the US is the TVA plant at Kingston, Tenn., with a nameplate capacity of 1,440Mw. Turbine-generator wits are also following a trend of ever-increasing size. In present construction, the 150 to 200 Mw size range for units ls the most common and represents the greatest contribution to capacity. Two units of 500-Mw nameplate rating each, the largest in the US, are on order by the TVA, and an 80 Mw unit is contemplated. (auth)

A brief review of the research work performed by the National Lead Company on the recovery of U from its ores is presented. A bibliography is presented which includes all reports on raw materials published by National Lead Company through Dec. 1958. Also included is a list of complete publications on raw materials from 1944 to 1954. (W.L.H.) low conditions at room temperature. Emphasis was placed on the effect of reaction parameters and mercury-recovery techniques on the Hg/sup 202/ content of the solid calomel formed in the reaction. For pure hydrogen chloride the Hg/sup 202/ content of the Calomel was found to be 39.9 plus or minus 0.3%, compared to the natural abundance of 29.8%. With 20 to 40 mole% of butadiene-1,3 in the hydrogen chloride, calomels containing 83 to 84% of Hg/sup 202/ were consistently obtained. The Hg/sup 202/ content of the calomel product was found to increase markedly when unsaturated hydrocarbons were added to the hydrogen chloride stream. The addends studied included butadiene - 1,3, benzene, isoprene, acetylene, propylene, and ethylene in order of decreasing effectiveness. From steady-state calculations the effectiveness of the addend can be shown to be determined by the rate ratio, k/sub 8// k/sub 4/. …

A study was made of the recrystallization behavior of beta-quenched uranium by incorporating the effects of transfer time from the beta heat-treating bath to the quench media. A critical transfer lime which relates to the time required to immerse samples at a temperature above the beta-alpha transformation in a quench media directly affects the beta-cooled structure and its ease of recrystallization upon alpha phase annealing. Within the critical transfer time, the ease of recrystallization and degree of grain refinement of beta-cooled samples as measured by alpha-phase annealing temperatures and times are superior to samples quenched beyond the critical transfer time. (auth)

Plutonium, thermally cycled through the low-temperature allotropic transformations, exhibited extensive physical damage. The physical damage was greater than that reported for any other metal or alloy. The extent of physical damage was determined by measurements of fluid displacement and the dimensional changes. The internal porosity was examined metallographically. Physical damage varied considerably, depending on the cycling conditions and the characteristics of the metal (particularly inclusions and casting imperfections). Observations showed that increasing the specimen size produced a greater decrease in density as a function of the number of cycles. The degree of void formation was directly proportional to volume change associated with the phase transformation. Other variables such as the length-diameter ratio (constant diameter) had little or no influence on the amount of physical damage. The dimensional growth was both radial and longitudinal. The tensile strength and the yield strength of tensile specimens cycled ten times between the gamnna and alpha phases were decreased to an average of 30,000 and 26,000 psi, respectively. (auth)