Tungsten in uranium--tungsten alloys is determined by precipitating the tungsten from a cold sulfuric acid solution using alpha -benzoinoxime and cinchonine as the precipitating agents. The precipitate is dgnited at 800 deg C and weighed as WO/sub 3/. Results of 94 determinations on known samples containing 20 to 40 milligrams of tungsten in the presence of 1 to 8 grams of uranium showed an average recovery of 100.1% with a standard deviation of 0.7%. (auth)

A report is made on the Kinetic Experiment on Water Beller Program. The purpose of this program is to examine the dynamic behavior of homogeneous research reactors to obtain the information necessary for the evaluation of the nuclear safety of such reactors. Step inputs of reactivity were systematically increased and the first test core, a spherical core designed for stable power operation at 50 kw, was examined under conditions of 4% reactivity release This is the maximum normally installed in such reactors A 4% reactivity release places the reactor on a 2 millisecond stable period and leads to a peak power of 530 Mw. This represents the fastest intentional power excursion of any thermal reactor. The reactivity released is more than twice that which any other has withstood without damage. The maximum pressure in the system for this transient was a sharp pressure peak of 370 psia. This pressure is well below that required to cause yield of a typical water boller core. (A.C.)

The KEWB Program is devoted to the study of the dynamic behavior of homogeneous type research reactors. The objectives of this program include studies to develop better and more complete understanding of phenomena which contribute to the kinetic behavior and the inherent safety of the water boiler reactor. The approach to the objectives has heen to construct a prototype 50 kw homogeneous reactor with the necessary auxiliary apparatus and to study the transient behavior of the system as a function of the more significant parameters which affect this behavior. These include the amount of reactivity release, rate of reactivity release, initial core pressure, initial core temperature, initial reactor power, and void volume above the core. Data are plotted. (auth)

Progress is reported in the following studies: the degradation of uric acid in man; the effect cf triiodothyronine on the oxidative metabolism of erythrocytes; the biosynthesis of abnormal proteins in multiple myeloma; tracer studies on the methbolism of DLglutamic acid in man; the effect of triiodothyronine on radiosensitivity of rats; the physiologic and clinical significance of erythropoietin; the measurement of isodose distributions from a revolving beam cobalt-60 therapy unit; tracer studies of protein binding and subcellular localization of digitoxin; applications of carbon-14 in methbolic studies; and tracer studies on the methbolism of progesterone. A list of publications during the period is included. (C.H.)

Absolute calibration of neutron yields from a polonium nitrate- fluorocarbon interface gave 8 neutrons/min, sq cm, mc/ml. In two Fluorox fluidized bed reactor runs UF/sub 6/ recoveries of 47 and 70% theoretical were attained. Washing and descaling operations for Loop P-1 have been completed. Preliminary studies of ThO/sub 2/ classification by hydroclones showed that particles as small as 0.5 micron could be classified. Continuous, self- sustaining operation of the Darex dissolver, stripper, and reflux condenser was maintained during a 48-hr period. Uranium losses to the sublimate were less than 0.1% in a 24 hr Zircex run. A 32 hr dissolution run was completed in which a fuel element fabricated of Zircaloy-3 was dissolved in a NaF-ZrF/sub 4/ fused salt. (auth)

The beta decay of the radioactive members of the mass-eight and -twelve triads has been studied with a spiral-orbit spectrometer having a 1.3% resolution. The end point, half-life and log-ft values respectively are: for N{sup 12}, 16.37 {+-} 0.06 MeV, 11.43 {+-} 0.05 milliseconds, and 4.17; for B{sup 12}, 13.40 {+-} 0.05 MeV, 20.6 {+-} 0.2 msec and 4.11; for B{sup 8}, 14 MeV (broad), 0.75 {+-} 0.02 sec, and 5.72; and for Li{sup 8}, 13 Mev (broad), 0.87 {+-} 0.01 sec, and 5.67. The mass excesses in millimass units are: for N{sup 12}, 22.48 {+-} 0.06; for B{sup 12}, 18.19 {+-} 0.06; for B{sup 8}, 27.08 {+-} 0.13; and for Li{sup 8}, 24.97 {+-} 0.09. The shapes of the Kurie function for the mirror pairs indicate positron and electron transitions to the same levels of the daughter nuclide, with greater percentages in the positron branches relative to the ground-state transitions because of the higher energy available. The Li{sup 8} and B{sup 8} shapes are consistent with the shape of the alpha spectrum following the decay of the Be{sup 8} daughter. Less than 1% of the Li{sup 8} transition and less than 5% of the B{sup 8} transition go to …

The velocity of sounmd in water containing bubbles of hydrogen gas is computed as a function of the volume fraction of gas for various bubble sizes. Results indicate that the marked reduction in sound velocity caused by the presence of gas voids is not as great if the gas is present as very small bubbles. The results are used in qualitative observations concerning inertial pressures in fast excursions in the KEWB reactor. The qualitative conclusions are listed. (J.R.D.)

This bibliography is a compilation of titles to unclassified reports, journal articles, and conference papers. The individual papers are divided into sections according to the year in which they appeared. (M.H.R.)

References to accelerators and accelerator technology in the technical literature from July 1954 through June 1957 are listed in Section 1, the bibliography. Most of the references are taken from Nuclear Science Abstracts, Chemical Abstracts, Physics Abstracts, and Electrical Engineering Abstracts. In Section H, accelerator installations throughout the world are listed together with the types of particles accelerated and the energy and other characteristics of the machines. (auth)

References to signiflcant design information for a steam generator in a gas-cooled reactor system are presented. Papers concerning heat transfer and pressure drop correlations for gas flow across banks of bare and circular finned tubes and for subcooled waters boiling water, and superheated steam flow inside pipes are listed and briefly discussed. (auth)

The design of the S3G and S4G reactor pressure vessel heads led to a study of perforated plates. A correlation of perforated plate theory with experimental data is given. The test results and analysis used for the S3G model tests are presented along with a review of two other experimental programs in which the experimental data were correlated theory. The conclusions reached indicate that the perforated lattice does, in fact, behave as an equivalent plate of reduced stiffness when subjected to transverse loading. The results obtained from the theory are sufficiently accarate for engineering applications for a range of plate sizes which extends from thin plates (radius-to-thickness ratio 7.5 to 1 for Duncan's tube sheets) to thick plates (radius-to-thickness ratio 1.6 to 1 for the reactor model head) with a variation in the number of penetrations ranging from the large number in Duncan's tube sheet tests down to the relatively small number (19 holes) ia the reactor model head (3/8 scale model). (auth)

The kinetics of the gamma deg C was con- beta deg C was con- alpha , beta deg C was con- gamma , and alpha deg C was con- beta deg C was con- gamma transformations were determined with a fiuid displacement technique. The rates of formation of the alpha and beta phases from the gamma phase were determined after gamma heat treating and allowing a sample to traasform isothermally in the alpha and beta ramges. Isothermal reaction curves were obtained from 160 C to -78C. The time-temperature-transformation curve of the gamma deg C was con- beta deg C was con- alpha transformation was plotted. The effect of the gamma heat treating time and temperature on the rate of transformation was examined. Isothermal reaction curves and time-temperature- transformation curves of the beta deg C was con- gamma , and alpha deg C was con- beta deg C was con- gamma transformations were plotted. Photomicrographs of specimens having transformed from the gamma range at different rates of transformation are presented. (auth)

The transformation kinetics of alpha and beta plutoniunn were determined by using a fluid displacement technique. The rate of formation of the alpha phase from the beta phase was determined after beta heat treating and allowing the sample to transform isothermally in the alpha range. Isothermal reaction curves were obtained from --78 to +90 d C. A time- temperaturetransformation curve showed the maximum rate of transformation to be approximately --20 d C. The beta phase did not transform completely to the alpha when the transformation was allowed to take place isothermally. A relationship between the fraction untransformed beta and the transformation temperature has been established. Isothermal reaction curves and a time- temperature-transformation curve of the alpha at 200 deg C an - BETA transformation were obtained. Portions of the timetransformation curves of the BETA at 200 deg C an alpha transformation of four purities were plotted. The effects of beta heat treating times and temperatures were studied. Photomicrographs of a specimen having transformed from the beta to the alpha phase at different rates of transformation are presented. (auth)

The identification of phases and interpretation of phase transformation through microstructural analysis are still difficult even with metallographic standards as a guide. Macrostructures provide a better guide to determination of the origin of the quenched phase and the degree of quenching. Grain sizes are of some assistance in determining the cooling conditions employed. Twinning concentration and grain boundry shape are inconclusive characteristrcs to use in determining the origin of the quenched phase and the degree of quenching. Subgrains are more prevalent in beta-treated uranium. Hardness profiles provide highly irregular data and are of little assistance in interpretation of heat- treating conditions. Single and multiple gamma-beta-alpha cycles appear severe enough to cause the formation of small voids in thc air-cooled zones of end quench samples. (auth)

The deflection and stresses of a medel of the Yankee lower core support structure, conslstlng of two clrcular perforated plates joined together by a clrcular reinforclng rib and 76 cylindrical spacers, were obtained experimentally. The relationships between the tests on the model and reference design were determined by an application of dimensional analysis. Experimental investigations are described in which various design parameters were determined and the structural rigidity of the assembly was obtained. A rational methed of semitheoretical analysis of the problem is suggested based on Reissner's small deflectlon theory which takes into account the effect of transverse shear and normal stress deformation. (auth)

The idea of ''antiparticles'', as is well known, originated with Dirac, who in establishing the relativistic equations for the electron noted that besides the solutions corresponding to ordinary electrons there were also ''unwanted solutions'' corresponding to particles of electronic mass but of charge +e instead of the electronic charge - e. The discovery of the positron by CD Anderson offered a brilliant experimental confirmation of Dirac's prediction and gave the first example of an ''antiparticle.''

A general survey is presented of information in the uranium alloy field. Emphasis is centered on alpha uranium-rich alloys of special interest as uranium- base fuel element materials. The systems treated include uranium-molybdenum, uranium-silicon, uraniumzirconium, uranium-niobium, and uranium-zirconiumniobium (high uranium compositions). The uraniumfissium alloys are discussed in relation to their projected applications as fast reactor fuels. Equilibrium diagrams, transformation kinetics, and other pertinent data are presented for the uranium plus fissium'' element systems, e.g., uranium-ruthenium, uranium-rhodium, uraninum-palladium, and uraniummolybdenum-ruthenium. The properties covered include constitution phase diagrams, metallographic structure, physical and mechanicaly properties, transformation kinetics, crystallographic structure, thermal cycling, ad irradiation stability (where pertinent). Correlations between microstructure, heat treatment, and dimensional stability are emphasized, with particular reference to the U-2 wt.% Zr, U-5 wt.% Zr, and 1 1/2 wt.% Nb alloys. A discussion of the role of alloying and heattreatment in improving the dimensionaly stability and corrosion resistance of uraaium is presented, and an evaluation is made of the present status in attaining these objectives. (auth)

Data are presented on the absorption of molybdenum on activated carbon. The effect of retention time and linear flow on absorption, the use of sodium hydroxide as an eluant, and the possibility of recovering molybdenum from the caustic eluate are discussed. (auth)

Low-frequency abeorption centers, observed by electrical measurements in single crystals of rutile, can be produced by thermal quenching or optical irradiation in the edge of the eigen absorption region (600 A). They are observed when electric fields are applied parallel to the optic axis (crystallographic c axis) and are not visible with the field perpendicular to this axis. The temperature dependence of the principal dispersion indicates an activation energy of 0.18 ev. The centers can be explained by a localized electron transfer process along the optic axis. The introduction of silver and copper by thermal diffusion did not produce low frequency absorption spectra. (auth)

The economic development of nuclear reactors depends upon the integrated progress in the fields of reactor design, fuel element design, reactor operation, and fuel production and separation. Broad criteria, which restrict the fuel element design, are determined by the mutual consideration of the problems encountered in all the above fields. Hence, no stage of reactor design or operation is independent of the fuel element problem, nor can the fuel element designer disregard the interest of any one field. As an introduction to the fuel element design problem, this chapter describes how the general criteria for a fuel element are determined.

The results of laboratory studies on sodium carbonate ion exchange are shown. The effect of salt concentration, uranium concentration, and possible interference with ion exchange from vanadium, molybdenum, sulfate and chloride are discussed. Various elution systems and the effect of residual uranium are described. A short discussion of ammonium carbonate ion exchange is also presented. (auth)

This report describes the operation of the fuels preparation department for the month of April 1958. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.

None

This is the monthly report for the Hanford Laboratories Operation, March, 1958. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.