A compilation was made of extraction data obtained for tri-n- octylphosphine oxide (TOPO). Diluents, oxidation states of the elements, type and concentration of acid, concentration of the metal and extractant, phase volumes, temperature, phase equilibrium, stripping, decomposition of metal adducts, and determination of extracted elements are discussed. lts extraction characteristics for the elements in each pericdic group are described. (M.C.G.)

The program was written for the Philco-2000 computer to provide a nuclear design computing tool equivalent to the IBM-704 computer program MUFT-4 and to provide a set of routines for a future spatial multigroup program, P/sub 3/ MG-1. In addition to the features of its 704 predecessor, MUFT-5 provides a more complete isotopic edit, an optional blackness coefficient edit, and the use of a complete P/sub i/->i>s library. The resultant program is found to be easier to use because of the simplicity of running several problems, more valuable because of the many additional results that are edited, and more economical because of the changes made in programming. (auth)

None

The results of an investigation into the effect of irradiation on the quality and integrity of several commercial siliocnized-silicon carbide (Si-- SiC) coatings for graphite are summarized. Si-- SiC-- coated graphites were oxidationtested at 1000 deg C in air both before and after irradiation. Data show that base graphites for coating must be fairly isotropic and must be stable toward high temperature radiation damage if the coating is to survive in-reactcr conditions. (auth)

Six examples are given of the application of analog computers in the fields of reactor engineering, heat transfer, and dynamics: deceleration of a reactor control rod by dashpot, pressure variations through a packed bed, reactor kinetics over many decades with thermal feedback (simulation of a TREAT transient), vibrating system with two degrees of freedom, temperature distribution in a radiating fin, and temperature distribution in an irfinite slab with variable thermal properties. (D.L.C.)

Reduction of small charges of uranium tetrafluoride with magnesium proved to be successful. By hand-tamping of UF/sub 4/-- Mg blend, tap densities ranglng between3.1 and 3.4 g/cc were obtained. The reduction yields for these densities ranged from 72.79 to 93.71%. In the case of machinecompacted UF4-- Mg blend having tap densities from 3.58 to 3.68 g/cc, reduction yields were higher, ranging between 91.45 and 97.2%. Machine-compacted blends gave much more uniform temperature distribution curves during the preheating period, as a result of higher tap densities. The best yields were obtained by firing a machine- compacted blend containing 5% Mg excess at a furnace temperature of 650 deg C, giving an average crude metal yield of 96.3%. However, the high carbon content of 174 ppm in the crude uranium biscuits obtained by compacts reduction, as a result of hydrocarbon binder presence, appeared to be a disadvantage. Attempts were also made to demonstrate the initiation of the reduction reaction at temperatures lower than 500 deg C by taking x-ray-diffraction patterns of the samples of the UF4-- Mg charges heated up to various temperatures. (auth)

The general differential equation of a thermally radiating fin is presented for the situation of a uniform heat source along the base of the fin. An electronic analog solution of a fin of nonuniform thickess with one- dimensional steadystate radiant heat transfer is presented. The specific example is concerned with a constant rate of variation of thickness; however, any general configuration could be used. (auth)

Nuclear reactor space electric power units under development in the U. S. include the SNAP-2, SNAP-8, and SNAP-10. The electric power output of these Systems for Nuclear Auxiliary Power (SNAP) extends over three decades of power, from 300 watts to 6O kilowatts. The major operational, installation, and handling characteristics of these nuclear power units are described. In particular, some limitations and restrictions with regard to payload, shielding, and radiation environment are described with respect to the power plants, their mode of installation, and system weight. The ground handling and safety, as well as the over-all safety, aspects of space reactor utilization are also described. The SNAP-10 power unit is a demonstration system that utilizes thermoelectric power conversion, The SNAP-2 power system utilizes a similar compact nuclear reactor, which is cooled with liquid sodium-potassium alloy, and coupled to a small mercury vapor turbine generator power conversion system. The SNAP-8 system is a direct outgrowth of the SNAP-2 power plant development. It wiil deliver 30,000 watts with one mercury vapor turbine generator system and weighs about 1400 (auth)

The maximum concentration of UO/sub 2/ (40 wt.%) was determined for stable, usable phosphate glasses. A number of such glasses were developed and probable structures

Data are presented from studies on the total Ra>s2/sup >> /ntent, radon retention, and activity of hotspots in human bones approximately 30 yr post- adiministration of Ra. Preliminary results are reported from a study of the incidence of bone tumors following injection of Pu>s2/sup >>,/a>s2/sup >>/ / sup ,/r>s9/sup >,/r Ca>s4/sup > / mice. Calculations were made of the radiation dose from hotspots formed in bone by these radioisotopes. The gamma spectra of 20 subjects who contained known quantities of K>s4/sup > /re obtained with several different sized NaI(Tl) crystals located at various points around the body. These spectra were analyzed to determine the variations in counting rates that resulted with each patient-crystal arrangement. The total-body gamma spectra of 12 unexposed employees were measured with the human spectrometer over a span of 30 mo. Data are tabulated on Co>s1/sup >>//s4/sup > /tios. The respo nse of a scintillation counter to gamma radiation asAa function of incidence angle was measured. Studies were made on the refractive index of selected optical media. Improvements were made in the design and in the scintillator solvent for a twin scintillation fast neutron detector. Measurements were made of the skeletal and soft tissue content of Ra …

The nuclear characteristics of the initial core loading for the Yankee Atomic Electric Company power plant are described. These characteristics include core reactivity, control rod and boron worths, and reactivity coefficients. In addition to operating characteristics, parameters for the cold and hot zero power cores are obtained for comparison with startup experiment data. Calculations to determine these characteristics are based on mechanical design specifications. (auth)

The energy loss spectra for gamma rays in NaI and CsI crystals were calculated by the Monte Carlo method. The calculations were carried out for point sources, broad and collimated parallel beams, and disc sources of monoenergetic gamma rays varying in energy from 0.142 to 14.0 Mev. The crystals considered were right circular cylinders. varying from small crystals of height and diameter of 0.5 inch to large crystals of height 12 inches and diameter 9 inches, and a sphere of 1-inch radius. Also calculated simultaneously with the energy loss spectra were the efficiencies and total absorption fractions. (auth)

The technique for adjusting the valence of Pu in the Pu(IV-VI) system to the Pa(IV) state for efficient solvent extraction or anion exchange is described. Investigations show that Pu(VI) may be reliably reduced to Pu(IV) with ferrous suifamate s. Nitric acid concentration must be between 2 and 6 M to avoid Pu disproportionation of suifamate precipitation. Ferrous sulfamate concentration is kept below 1 M to prevent crystal formation after the reaction, but Pu concentration may be as high as 250 g/l. (P.C.H.)

Summaries are given of the activities of the Nuclear Chemistry Division during 1960, in radioactivity and nuclear spectroscopy, fission, nuclear reactions, physical chemistry, instrumentation, and chemical engineering. Included are abstracts of graduate theses awarded during 196O for work conducted in the Division. (B.O.G.)

The studies were primarily directed toward selection of the optimum loading for Core lA and a prediction of its properties. Included are analyses of some relevant experiments on Core 1, and prelimlnary modifications of Core 1 to Core lA. The factors which must be considered for the optimum loading determination are discussed. Four different loading pattenrs were investigated, which were considered to span the numerous possibilitles. Adequate cold shutdown was found to be almost unobtainable without the use of boric acid. For this reason, and because the heat transfer and stability limitations are severe, greater weight was given to heat transfer as opposed to control requirements. The use of boron-stainless steel poison strips fastened to the sides of the spike elements is considered insofar as in improving the loading from either the heat transfer or control standpoint. The relatlve advantages and disadvantages of the use of stainless steel fuel followers as opposed to Zircaloy followers are discussed. (B.O.G.)

A definitive investigation of the boron-carbon equilibrium system is being made by x-ray diffraction, metallographic, and thermal analytical techniques. On the basis of metallogaphic and x-ray-diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 at.% carbon at 1500 to 2000 deg C. The melting point of the carbide-graphite eutectic was established as 2325 to 2350 deg C. No reversible allotropy of the beta -rhombohedral structure was observed. The solubility of carbon in boron is very small. The melting point of dilute carbon alloys is found to be essentially the same as that of pure boron (2040 to 2050 deg C). No metallogaphic evidence of a three-phase reaction of dilute alloys is observed. (auth)

None

The iteration sequence used in the multigroup Program F-N (ANP No. 308) in which one energy lattice sweep, a so-called inner iteration, is performed for each space power distribution sweep, an outer iteration, exhibited a painfully slow convergence rate in the presence of significant "up-scattering" even for the typical ANP reactor where the dominance ratio between fundamental and first harmonic space modes is about five. A revised iteration sequence in which the energy lattice sweep is iterated to a desired convergence before repeating the power iteration is outlined. The revised procedure should significantiy reduce the machine time required for this type of problem. (auth)

The development of remote fabrication methods and equipment in which the cooling periods, chemical fission product separation, and complete decontamination of the fuel is not required is discussed. A process designed around precision casting in multiple, glass molds served as a basis for design of refabrication equipment. The injection casting process is used. Procedures and equipment were developed for the remote manufacture of right-cylindrical, uranium alloy fuel pins from the castings. Assembly, welding, and leak testing of the EBR-II fuel rods are described. Methods of sodium bonding and bond testing are described. (M.C.G.)

>The mechanical and physical properties of Zircaloy-2 were determined as a function of five test variables: temperature, grain size, direction to rolling, hydrgen content, and the presence or absence of a notch. The investigation included studies of the coefficient of thermal expansion, elastic moduius, tensile properties, creep properties, and low-cycle fatigue properties. Approximately 470 specimens from a single ingot were tested in the course of the investigation. (auth)

Weekly newspaper from Taft, Texas that includes local, state, and national news along with advertising.

Daily newspaper from Ada, Oklahoma that includes local, state, and national news along with advertising.

Weekly student newspaper from McMurry College in Abilene, Texas that includes local, state and campus news along with advertising.

Daily newspaper from Elk City, Oklahoma that includes local, state, and national news along with advertising.