An apparatus was developed for recording internal friction data in such a manner as to circumvent many of the laborious and time-consuming observations and calculations usually associated with these measurements. An optical lever is used and the passage of the beam across the scale is detected by photoconductive cells. The cells are strategically located so that, when their signals are fed through a multichannel switching circuit to the pens of an operation recorder, a plot of the logarithm of the vibrational amplitude versus the number of cycles is recorded on the chart. From the definitmon of the logarithmic decrement, ( delta ), it can be shown that the slope of this curve is - delta . The apparatus is inexpensive and requires a minimum of maintenance. It has been used for accurate determinations of values of delta from below 0.0001 up to 0.3. (auth)

Twenty-three papers are included which were presented at the Conference on Organic Scintillation Detectors. The topics treated range from measurements of organic phosphor properties to liquid and plastic scintillation detectors. Separate abstracts were prepared for each of the papers. (D.L.C.)

Results of crawing experiments using 3/8-in. bars to provide rod and tube test specimens are reported. In mechanical metallurgy investigations on the relation of formability to imperfection structure the peierls potentials for dislocation of Nb, Mo, Ta, and W were measured. Design and construction of a microextensometer reported. The investigations of the effects of grain size on the stored energy cold work were extended to a new lot OFHC Cu. In studies of formability relations with imperfection structure, a detailed study is reported on the internal-friction relaxation spectrum of Ta relatively unmodified by impurities. A summary of interstitial impurity effects on the internal-friction of Ta is given. (J.R.D.)

BS>Activities are discussed for work done in the preparation of PuO/sub 2/ using the continuous oxalate process, and continuous coprecipitation studies using a uranium-20 wt% plutonium nitrate feed solution. Characterization studies of the PuO/sub 2/ powders indicated that variations in the processing variables can affect the final product. Measurements with the B. E. T. and Innes apparatus confirmed that the specific surface area of the initial batch of the PuO/sub 2/ powder had increased appreciably during storage. Deltatherm differential thermal analysis apparatus was checked out. Procedures were devised for the determination of plutonium and uranium. Sintering studies were continued for pure PuO/sub 2/, and sintering trials were begun for mechanically mixed and coprecipitated PuO/sub 2/ and UO/sub 2/. Metallographic examinations of PuO/sub 2/ sintered pellets revealed a microstructural feature similar to eutectoid structures in alloys. Mechanical packing experiments were carried out using crushed UO/sub 2/ pellets fired to high density. Plasma torch production of UO/ sub 2/ indicates that excellent spheroidization is attained, but central voids were found in the pellets. Reactor physics studies were completed for the analysis of the potential of plutonium as a fuel in near-thermal converter and straight burner reactors. Plutonium was shown to be promising …

The development of apparatus and laboratory techniques for the study of materials compatibility with 1500 to 2200 deg F potassium was attempted. Techniques for corrosion tab preparation, dry box capsule filling and sampling, and vacuum filling and sampling are described. Apparatus for rotating capsule testing to 2000 F, rotating capsule testing to 2400 deg F, and anisothermal see-saw'' capsule testing is also described. (auth)

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An extensive parametric study of cesium-filled converters was completed during the quarter. Cesium-filled test units Nos. 2 and 3 were designed and constructed, and Unit 1 is 85% complete. The prototype vacuum thermionic converter, Unit 2B, was subjected to dynamic testing following its failure due to emitter poisoning. The analysis and design of the curium fuel capsule were completed. (auth)

Progress and results from the conceptual design, economic evaluations, and research and development work performed as part of the Nuclear Superheat Project are reported. Developments in conceptual design and program evaluation, fuel technology, materials development, experimental physics, coolant chemistry, heat transfer, mechanical development, SADE, and mixed spectrum superheat design are discussed. (M.C.G.)

The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulation of a reactor as a feedback control system was adapted to VBWR. Equations for the hydraulics model and preliminary results from use of the model are presented. Irradiation of the Fuel Cycle stainless steel clad assemblies reached 412 MWD/T with specific powers of 28 kw/kg (average) and 52 kw/kg (peak) during January. Visual examination of the fuel after this irradiation indicated that it is in good condition. The VBWR was shut down during February and March for replacement of all in-core components made of 17-4 pH stainless steel with 304 stainless steel. The details of the first eight special fuel assemblies were determined and materials were ordered. The effects of steam quality, mass flow rate, and rod diameter on burnout heat flux are shown. The burnout heat flux varied inversely with mass …

This report follows an investigation made to determine creep-rupture data for three sheet materials. Fourteen of sixteen tests were made in an atmosphere of carbon dioxide within hermetically sealed capsules, analyzing the reaction of the three sheet metals: 347 stainless steel, iron-aluminum-chromium alloy designated 261C, and a zirconium-base alloy, AE1H. Minimum creep rate, per cent elongation, and rupture life were determined and reported.

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This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1961. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of July through December 1961. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to December 1961.

The effect of the many parameters which may influence the failure behavior of coextruded fuel material are being evaluated by Reactor & Fuels Research & Development Operation. This knowledge will be helpful in the design, fabrication, and operation of fuel elements so that the hazards and time involved at failure may be minimized. Many of the various tests performed on unirradiated coextruded fuel material have been in isothermal systems. The tests reported here were performed on power generating coextruded fuel rods. One of the purposes of these tests was to assess the effect of simulated in-reactor power generation and associated thermal gradients and thermal stresses on the defect-test behavior. Another purpose of these tests was to determine the degree of damage that might result to fuel components as a result of interaction (e.g., touching produced by warping or distortion of a failing rod) while at operating powers.

Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.

A discussion is given of a fabrication process for preparing spherical particles of thorium oxides containing 10 wt.% uranium homogenously distributed throughout the thoria matrix from a sol prepared from Th(NO/sub 3/)/sub 4/ reaction with NH/sub 4/OH, in which uranyl nitrate is dissolved. The particles formed are 5 to 50 microns in diameter. The process is felt to be adaptable to large-scale production. (B.O.G.)

Work was begun to determine the physical properties of mica-filled diallyl phthalate. Both the impact and tensile strength values compared favorably wlth asbestos-filled DAP formulatlons. The tensile values compared with the upper limit tensile strength values for asbestos-filled formulations. Adiprene-ferric acetyl acetonate-polyol systems were developed as adhesives and their properties studied. Sources of kilogram quantities of Th/sup 2//sup 3//sup 0/ were investigated. The samples were analyzed by a direct CeF/sub 3/ precipitation procedurc or by a tributyl phosphate-cerium procedure. The half- life of Ra/sup 2//sup 2//sup 3/ was found to be 11.3700 plus or minus 0.0065 days. Differential thermal analyses were made of lanthanum and praseodymium metals. Three preilminary determinations of the density of molten cerium were made by the vacuum pycnometer method. An average value of 6.58 was obtained. Leaching tests in water and in 0.1N HCl were continued on fibers of an experimental glass containing 10 wt.%n plutonium oxide. (M.C.G.)

The object of this experiment was to extrude normal uranium hollow billets to I and E `O` size tubing with reduced extruded O.D. and also to evaluate the use of pressed salt follower blocks. Pressed salt (NaCl) follower blocks under various conditions of pre-heat temperature were compared with the standard graphite at 800 F. Even though some yield reduction results, it was concluded that pressed salt follower blocks at 300 F represent a substantial cost reduction due to the extreme price differential of the two perishable items. Extruded O.D.`s of .020 inch and .040 inch less than the standard (nominal) 1.50 inch represent no gain in yield due to the sharp increase in machined slug rejects for O.D. defects.

The absolute differential cross sections for elastic scattering of 31- Mev He/sup 3/ ions on Be, Al, Cu, Sn/sup (nat)/, Sn/sup 120/ and Bi were measured in the angular range of approximately 10 to 120 deg in the center-of-mass system. Thin selfsupporting foil targets were chosen to span the parameter A/sup 1/3/, where A is the target mass number. The first excited states of the isotopes of these elements had sufficient energy separation from the ground state to enable elastic scattering to be resolved from inelastic scattering. The detection system, consisting of CsI(Tl) scintillation crystals, was capable of 3% pulse- height resolution and 1 degree angular resolution. Characteristically, the light- element angular distributions show strong diffraction effects. The differential cross section divided by the Rutherford cross section decreases exponentially at large angles for the heavy elements, and the differential cross sections break away from Rutherford behavior at angles which increase almost linearly with increase of atomic number of the target nucleus. A comparison of the results for natural Sn, and Sn enriched to 85% in Sn/sup 120/, indicated that within the experimental uncertainties over the measured angular interval, there were no pronounced isotopic effects. The data are presented both in …

Activities in a program to develop techniques of plasma spraying clad plate-type UO/sub 2/ fuel elements are reported. The investigation was also directed toward determining the limitations of the process as applied to fuel element fabrication. UO/sub 2/ powder coatings having densities of 90% theoretical were produced. At conditions required for spraying plates, densities of 86% appear to be practical. The rate and efficiency of UO/sub 2/ coating deposition were also determined for various spraying conditions. Gritblasting was found to provide the best surface for coating adherence. The O/U ratio of the UO/sub 2/ was maintained by spraying in an Ar atmosphere. Zircaloy-2 was found to be the most desirable cladding material. Cladding thicknesses of 0.035 in. are required in distortion-free 2-in.-wide plates. (J.R.D.)

Progress made in the development of the Cs/sup 137/ fueled thermoelectric generator for marine power applications is reported. Information is given on thermoelectric generator design, shielding, power conversion system, hazards evaluation, fuel element forming and cladding, fabrication, and heat transfer. Cs/sup 137/ energy calculations are presented along with shielding calculations. The development and fabrication of cesium polyglass for fuel application are included. (N.W.R.)

Progress is reported in 26 papers on radioactive waste disposal, ecologicah research, radiation physics and dosimetry, internal dosimetry, and health physics technology. Twenty-five separate abstracts were prepared. One paper was previously abstracted for NSA. (M.C.G.)

Results of studies of the known parameters for direct calcination of plutonium nitrate in an agitated bed and conversion of PuO/sub 2/ to PuCl/sub 3/ by fluid bed processes are presented. A description of the processes and the demonstration equipment is included. The study of variables is discussed along with the parameters and plans for demonstration runs. (J.R.D.)

Coatings on the fuel element surface and coatings on individual fuel particles are being investigated for retaining fission products in fuel for the Pebble Bed Reacter. Ten fuel element specimens with surface coatings were subjected to varying amounts of high level irradiation. Cracks or pinholes were found in 6 of the coatings. Evidence indicated that the graphite matrix contributed to most of the failures. Release factors of the order of 10/sup -9/ for the Si--SiC coating under high-level irradiation existed for a period of about one month, however. The pyrolytic carbon coating showed some promise as a fission product barrier in several neutron activation tests. Fourteen batches of UO/sub 2/ particles were coated with A1/sub 2/O/sub 3/ by the vapor deposition process. Tests showed that this coating is an excellent barrier to fission products. In pyrolytic carbon-coated UC/sub 2/ particles there is no temperature limitation due to reaction between the particle coating and the graphite matrix. (M.C.G.)

Experimental results were obtained on the effect of an ultrasonic field on the burnout heat flux for water flowing at atmospheric pressure, through an annular flow channel formed by a 1/4-in.-diameter electrically heated tube and a concentric glass tube of 3/4-in. ID. The active length of the central heating element was 5 1/2 in. The ultrasonic transducer, which was operated at 25,000 cps and a maximum electrical input of 300 watts, was located at the inlet end of the flow channel. The ultrasonic waves were propagated in the water in the direction of flow and thus parallel to the surface of the heating element. Burnout conditions covered channel inlet flows from 1.61 to 6.25 ft/sec and subcooling from 16 to 28 deg F. No effect of the ultrasonic field on the burnout heat flux or on the visible boiling phenomena at burnout conditions was detectable. During boiling at heat fluxes well below burnout, the effect of the ultrasonic field was a reduction in the diameter of the envelope of bubble activity surrounding the heating element. Visual inspectibn appeared to show that this reduction was associated with a smaller average bubble size and a greater frequency of bubble formation. However, all …