A pyroelectric carrier distillation method, using sodium fluoride as a spectroscopic carrier, was developed for the impurity analysis of plutonium metal. (auth)

Tables of data calculated on an IBM 610 automatic computer are given to convert the measured pressure differences in the Van Slyke gas analysis apparatus into micromolar concentration of gas in solution for hydrogen, oxygen, carbon dioxide and carbon monoxide in water. Measured solubility coefficients for carbon dioxide in various aqueous solutions of formic acid are given together with the conversion factors for use with the Van Slyke analysis apparatus. (auth)

BS>The ten transuranium elements discovered since 1940 are discussed in chronological order. The discoverer, the history, and methods used are given for each element. Future developments in the discovery and preparation of transuranic elements are discussed. (A.C.)

A method for the safe handling of the SNAP-III thermoelectric generators is presented. It provides information regarding shipping regulations, general handling instructions for packing, unpacking, and demonstrating the device, and procedures to follow in an event of an accident. Possible hszards involved in handling the device, and the probability of any of these hazardous incidents occurring while it is being demonstrated, are summarized. Containment of the radioisotope fuel used in the SNAP-III device was assured under rigorous conditions, including short time external thermal temperature excursions to 1600 deg C, when in the shipping container. The probability of the device encountering such temperatures are remote. (auth)

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A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth)

A steady-state hot wire method for measuring the thermal conductivity of light gases in the temperature range 1200 to 2100 K is described. In contrast to other methods, free convection currents and large temperature gradients occur; convection effects are shown to be negligible, and an experimental procedure for eliminating the large gradient effects is described. The thermal conductivity of helium is found to follow the equation deg F. Cores o x 10/sup 6/ = 991 + 0.678(T - 1200) cal/sec cm deg over the temperature range covered. That for hydrogen is deg F. Cores o x 10/sup 6/= 1434 + 1.257(T -12OO) cal/sec cm deg. (auth)

Uranium dioxide pellets sealed in Type 316 stainless steel containers with a helium gas were irradiated in helium and in C0/sub 2/ in thermal fluxes or the order of 1 x 10/sup 13/ n/(cm/sup 2/)(sec). Cladding-surface temperatures were reportedly between 1200 and about 1800 F. The hot-cell examination performed by BMI showed that there were no obvious effects of the irradiation on the specimen tested in helium. However, the specimen irradiated in the presence of C0/sub 2/ exhibited severe cladding-CO/sub 2/ reaction and possible central melting of the UO/sub 2/. Although comparisons between pre- and postirradiation data were difficult because of involved fabrication history of the specimens, the tests did further establish the fact that helium is a satisfactory coolant gas for stainless steel cladding material at a temperature of 1200 F. The data obtained from the specimen tested in the presence of C0/sub 2/ indicate that at temperatures in the range of 1600 to 1800 F Type 316 stainless steel is not compatible with C0/sub 2/. (auth)

Free energy functions for gaseous nmonoxides were calculated from presently available spectroscopic results. However, the electronic contributions to the free energy functions were estimated. A simple ionic model was assumed since the molecular electronic states for most of these oxides are not known. In some instances where experimental data are insufficient to calculate the interatomic distances and the equilibrium frequencies of vibrations, they were estimated. The results of these calculations are tabulated for every 500 interval from room temperature to 3000 K. (auth)

The atomic-beam magnetic-resonance flop-in technique using radioactive detection was employed to measure the nuclear spins doff B/sup 206/ , Ti/sup 200/ , Tl/sup 201/ Tl/sup 202, In/sup 09. ln/sup 110m/ and In/sup 111/. In addition the magnetic-dipole and constatns of In/sup 109/, In/sup 110m/, ined. the signs of the In/sup 110m/ con-, stants were not determined. Results, theory, procedure, and data reduction are given. (auth)

The preferred orientation of a relatively small piece of high-purity uranium rod, rolled to an 85% reduction at 300 deg C, has been determined in the as-rolled and in the recrystallized conditions. The 12 different charts obtained indicated that the as-rolled texture could be described as a duplex (041) and (352) with the (041) being the major component and with considerable spread about each component. The recrystallized rod showed approximate (041) and (392) components with considerable spread. These texture components for both the as- rolled and the recrystallized rods are not too different from those previously reported for reactor-grade uranium rod. However, it was noted that the texture appeared to be quite sharp for the reduction used, and the maximum intensity on an inverse pole figure was considerably displaced from the periphery of an (001) standard projection for both the rolled and recrystallized rods. (auth)

Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions were continued. Additional deposition tests were carried out in loop L-2-23 in which the core section was heated. Several reagents were tested to determine their ability to dissolve stainless steel corrosion products. A simulated HRT fuel solution was stable with regard to U concentration when diluted to 23 ppm at 250 C; however, some Cu was lost from solution. Preliminary tests in a uranyl sulfate solution indicate that an 18-8 stainless steel alloyed with either small amounts of Pt or Cu is more corrosion resistant at low flow rates than a conventional 18-8 stainless steel; however, the addition of either Cu or Pt did not reduce the corrosion rate of 18stainless steel at high flow rates. A study was made to determine the susceptibility of off-specification type 347 stainless steel to intergranular attack by uranyl sulfate solutions. Continued testing with a single heat of cast type 347 stainless steel has confirmed previously reported data to the effect that the cast alloy is more resistant a stress-corrosion cracking than is the wrought alloy. Six commercial grades of Al/sub 2/O/sub 3/ suitable for use as check balls in …

The CUREBO code for the IBM 704 is described. The code is divided into three parts including the calculation of nuclear cross section of the various physical components of a reactor (WOX7), the solution of the multigroup diffusion equations in two-space dimensions in order to find neutron fluxes and sources for an operating reactor containing these components ( CURE), and the calculation of fuel and poison depletion as a result of operating this reactor under steady- state conditions (BO2). (auth)

Neutral hyperons produced by 5-Bev The effects of /sup -/ mesons incident on a large propane bubble chamber are analyzed in detail with respect to production cross sections and angular distributions of production and decays and the A lifetime is measured. The cross section for neutralhyperon (Y/sup 0/) production by the reaction The effects of /sup -/ + p 1100 deg C are Y/sup 0/ + K is 0.98 sintering time 0.16 mb. The cross section for carbon mpacting ( The effects of - + C 1100 deg C are Y/sup 0/ + K) is 6.05 sintering time 0.89 mb. The mean Svlvania Electr decay time is (3.12 sintering time 0.34) x 10/sup -10/ sec. The corrected lifetime is observed to be (3.23 sintering time 0.36) x 10/sup -10/ sec. Although the up-down decay asymmetry for Svlvania Electr hyperons is not significantly different from zero, the fore-aft decay angular distribution is asymmetric; alpha P = -0.31 sintering time 0.12 where the decay proton distribrtion along the Svlvania Electr direction of motion has been examined. This is suggested as evidence for nonconservation of parity in the production interaction. The Svlvania Electr -production angular distribution is peaked backward in the production center …

Papers contained in this report supplement a book of papers published in 1958, American Institute of Chemical Engineers, Hew York. Eighteen papers are presented on designs eqaipment, and operation of hot laboratories. Minutes of a round table panel discussion presented at the conference are included. (W.D.M.)

Wind tunnel testing of swept wing fighter aircraft model for determining drag and static longitudinal and lateral stability and control characteristics. Results regarding performance, longitudinal stability, lateral stability, and strakes are provided.

>A 10-year program of development and construction of large-scale, sodium-cooled reactors is summarized. The current state of development of the SGR and its associated components is sufficiently advanced to permit construction of economic plants within the 10-year period. Two advanced Sodium Reactor concepts are presented. A construction program involving two reactor experiments and two full-scale plants with a capacity of 550 Mwe, together with associated development, is estimated to cost 6 million. Of this amount approximately 06 million would be borne by the AEC and the remainder by power utility companies. Escalation and construction loan interest charges are included in these figures. The cost of power from the larger power plant would be approximately 6 mills/kw-hr, based on 1959 dollars. (auth)

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The Cd/sup 115m/ and Cd/sup 115/ isomers produced in 12- to 340Mev proton bombardments of U/sup 238/ were isolated by radiochemical methods. The cumulative yield ratios of Cd/sup 115/Cd/sup 115m/Cd/ were determined. In the 45- Mev heliumion flssion of uranium, an estimation of the independentyield ratio of Pm/sup 148/ (5.3-day) to Pm/sup 148/ (43-day) was made. In the deuteron fission of uranium at about 20 Mevs an estimate of the independent-yield ratio of Nb/sup 95m/ to the total niobium of mass 95 was made. A literature survey on experimental isomer ratios from fission was made. The yield ratio of Sc/sup 44// Sc/sup 44/ was measured in Sc/sup 45/ ( alpha , alpha n)Sc/sup 44/ reactions with helium ions of energies between 20 and 43 Mev and at 320 Mev. The Sc/sup 44m/Sc/ sup 44/ ratio was measured in K/sup 41/( alpha ,n)Sc/sup 44/ reactions at 10 and 43 Mev. The compound-nucleus model was used to calcalate the Sc/sup 44m/Sc/sup 44/ ratios produced by the reactions /sup n44/ and Sc/sup 45/(p,pn)Sc/sup 44/ at energies 0.4 Mev above threshold. Agreement between the experimental and calculated Sc/sup 44m/Sc/sup 44/ ratio was obtained for the K/sup 41/(l0-Mev alpha ,n)Sc/sup 44/ reaction. A classical knock-on …

OR XLS 1-5 is a program for structure factor calculation and for the least squares refinement of crystal structures using x-ray or neutron diffraction data. The code is divided into five segments, and the purpose of each is briefly described. (W.D.M.)

>The program described computes the reactivity changes associated with slurry settling in a one-region cylindrical slurry reactor. Nuclear-data computation has been included in the program in order to avoid tedious hand calculations and to reduce the amount of input data required. About 3000 cases may be processed pcr hour of machine time. Certain modifications to the conventional two-group method and techniques employed in improving the rate of convergence of certain iterative procedures are discussed in detail. Sample input sheets, output sheets and instructions for input data preparation are included. (auth)

A group of uranium specimens were irradiated under conditions in which some of the specimens were irradiated continuously while others were cycled in and out of a reactor. Although most of the specimens were irradiated under conditions in which they were entirely in the alpha phase, some were irradiated so that their centers were above alpha-phase temperatures. Both highly textured material (300 deg C rolled) and nomimally randomly oriented material (300 deg C rolled and beta-quenched) were studied. It appeared that irradiation cycling of both types of material may result in greater elongation than would be anticipated on the assumption that the effects of irradiation and thermal cycling acting alone were additive. The material rolled at 300 deg C showed no external effects due to central irradiation temperatures being above those limiting the alpha phase. However, betaquenched material, which was irradiated so that central temperatures were above those required for stability of the alpha phase, developed severe distortions which were greater under cycling conditions. It was also noted that 300 deg C rolled uranium begins to elongate under irradiation at burnups as low as 0.0002 a/o (2 Mwd/t). (auth)

Aqueous entrainment in the extract from the first refinery pamper- decanter was found to range from 0.7 to 2.4 volume per cent. About an order of magnitude better decontamination for sodium and similar impurities is obtained by centrifuging the organic extract. The amount of water sorbed by green salt under equilibrium conditions is a linear function of the uranyl fluoride content. Uranium tetrafluoride could not be dried in air above 400 deg C without serious decomposition. Experiments with isotliermal'' laboratory-scale bombs indicate that preignition charge temperatures above about uranium. An upper limit of about 400 deg C on this heating was necessary to minimize premature ignition. The thermoconductivity of a laboratory bomb charge was increased by replacing pant of the normal granulated mangnesium with magnesium strips or larger chips. The lowest ignition temperature of heated, stirred magnesium-green salt mixtures was found to be 393 deg C. This indicates that preheated bomb charges could probably be handled safely at temperatures below about 300 deg C. A high-voltage spark discharge ignited a cold mixture of UF/sub 4/ in magnesium. The replacement of normal bomb lids and MFL charge caps with either porous graphite or ffrebrick produced uranium with lower hydrogen than normal …

A study was made of the effect of carbon, manganese, oxygen, palladium, and sulfur on the structure and fabricability of iron-35 wt.% chronium-1 wt.% yttrium alloy. Using a vacuum-induction melting technique each of the additives except oxygen was introduced to 1-lb remelts of a single 15-lb master alloy. The master alloy and remelts were made under similar melting, pouring, and casting conditions. Oxygen was introduced as Fe/sub 2/0/sub 2/ by inertelectrode arc melting to avoid extraneous, uncontrolled contamination stemming from crucible contact. Photomicrographs were prepared of as-cast metal illustrating structural variations. Ingots obtained were fabricated to 0.050-in. sheet at 2000 deg F to compare fabrication characteristics with those of the control ingot containing no additives. As a qualitative measure of metal soundness and ductility, a portion of each of the 0.050-in. sheets was further reduced at room temperatare to 3-mil foil. During melting at 2900 to 3000 deg F under controlled conditions, the amount of yttrium present in the charge was reduced roughly 50% by reaction with the alumina crucible. Sulfide, added as FeS, and oxide additions also lowered the amount of yttrium retained in ingots. The maximum amount of sulfur retained in an alloy of nominal composition iron-35 wt.% …