The status of development studies being conducted on a pebble bed power reactor is outlined. The items discussed are fuel element manufacture, stability, and reprocessing, and component development. (D.L.C.)

This report addresses the advanced energy sources and conversion techniques.

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The basic design and development concepts are presented on a six vane air motor intended for use at elevated temperatures. (auth)

As a result of a wide variety of studies on photosynthesis in living plants and plant fragments, together with the development of photosensitive, photovoltaic junctions in inorganic crystals and the discovery and exploration of semiconduction in organic molecular substances, a suggestion has been made that the primary quantum conversion process in photosynthetic tissues involves the creation and separation of charge to opposite sides of an asymmetrically-constructed lamina, followed by the trapping of both the electrons and the holes which then lead to their respective chemical processes, namely reduction of carbon dioxide and oxidation of the water to oxygen. This has led us to study model systems as semiconductors with a view to creating an organic photovoltaic junction.

A description of the new Weldon Spring Feed Preparation and Sampling Plant for uranium concentrates is given. Prior to the startup of this plant the auger to be later installed was used in an evaluation program to test reliability for representative sampling and uniformity both within drums and between drums of various concentrates. Results of this program were used as a reference for the sampling plant evaluation which involved successive auger and mechanical sampling of a series of lots of several concentrates, followed by moisture determinations, uranium assays, and statistical analyses of the data. From the final results conclusions are drawn concerning the suitability of the mechanical sampling system for the concentrates examined.

In order to investigate the rupture stability of uranium elements irradiated at power generations per unit length larger than those encountered in natural uranium fuel elements, three partial columns of 1.44% U{sup 235} enriched, internally-externally cooled, uranium elements were irradiated in PT-IP-1-A. After discharge and examination of the fuel elements 25 pieces (182.5 pounds) of this metal were available for special analysis of U{sup 235} burnout and plutonium content. The average exposure of these pieces was 2,187 {+-} 6% MWD/Ton. The purpose of this document is to summarize some calculations of buildup of plutonium isotopes and burnout of U{sup 235} in an attempt to correlate calculations with the results from experimental analysis.

Beginning in February, 1958, a sufficient quantity of seven-inch dip canned I & E depleted uranium fuel elements was prepared for irradiation to produce eleven kilograms of plutonium, containing at least twenty per cent of the Pu-240 isotope, as authorized by the Atomic Energy Commission. Subsequently, eighty-four columns in C reactor were partially charged with the finished depleted fuel under PT-IP-132-AC. To date, ten depleted ruptures have been sustained, after being irradiated six to eight months toward a planned accoumulated goal exposure of 210 MWD per column or a total irradiation time approximating 12--14 months. The mechanism and cause of these failures is being thoroughly investigated. This document summarizes the fabrication history, irradiation experience to date, rupture examinations, and an investigation of process conditions which may have contributed to the high incidence of ruptures.

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In this document it is proposed to describe the plant site and to outline the nature of the pile in order to show the specific design and layout requirements for the production of plutonium by nuclear synthesis. The selection of the plant site involved a number of special considerations. An essential requirement was a large dependable supply of relatively pure water that remains at a fairly low temperature throughout the year. A large source of power was required to circulate the tremendous quantities of water. The potential dangers connected with the high energies of the nuclear reaction and the formation of a large quantity of radioactive by- products required large distances between each operating section of the plant, and between the plant and main rail and highway routes. The plant site layout and reactor areas are discussed in the first part of the chapter, followed by a functional description of the more essential pile components. The chapter concludes with a discussion of reactor instrumentation. 24 figs., 2 tabs.

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.''

In this discussion of the heaviest known elements, the author describes some recent research which appears to offer the most promise for future investigations. As a general background, the author reviews briefly the history and properties of the transuranium elements.

The discovery of the delayed light emission of plant materials by Strahler and Arnold in 1951 has stimulated a good deal of interest in this rather remarkable property. The emitted light has been shown to be due to an electronic transition between the first excited singlet state of chlorophyll and the ground state. At room temperature, a luminescence is observable from about 0.01 seconds to several minutes after excitation. Thus, the electronic transition cannot be rate-determining and the process represents neither normal fluorescence nor normal phosphorescence. Indeed, there is some evidence that the decay curve of the luminescence is the resultant of more than one rate-limiting process. Strahler and co-workers have been able to demonstrate the existence of many relationships between delayed light emission and photosynthesis and thus have been led to interpret the luminescence phenomena as a consequence of the reversibility of some of the enzymatic photosynthetic reactions. Moreover, Tollin and Calvin have shown that the faster decaying components of the delayed light are present to as low a temperature as -100 C, suggesting that the early processes following light-absorption are non-enzymatic in nature. These latter observations, in conjunction with several other types of experimental and theoretical information, have …

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The Civil Effects Test Operation Exercise CEX-57.1 following Operation Plumbbob was carried out to obtain information on decontamination procedures that could be used as radiological countermeasures. The test was conducted on D + 1 and D + 2 days after shot Coulomb C. Data were obtained on reclamation of land areas by scraping with a motorgrader, on fire-hosing and scrubbing a concrete- slab roof, and on fire-hosing a composition roof. In addition, some shielding data were obtained for a small building with 6-in.-thick concrete walls and roof. The conceptual nature of a radiological defense system and the role of decontamination or reclamation in such a system are discussed. Most of the report deals with methods for reducing the observed data to interpretive form because the data were taken within a large contaminated area. The decontamination effectiveness in terms of the fraction of contamination remaining was computed. It is concluded that low levels of contamination at the Nevada Test Site could be utilized to advantage to obtain data on gamma -radiation properties, such as the effects of materials and source geometries on the attenuation of fission-product gamma rays. However, higher levels of fall-out in terms of the fall-out particle mass, are …

The operation of the tests and experiments conducted in the ORR, the LITR, and the ORNL Graphite Reactor is discussed. In order to minimize the possibility of any hazardous conditions developing into an incident involving the safety of personnel, the reactor, and other equipment, any experiment design and installation should be checked or reviewed to ensure that all conceivable dangers are recognized and that appropriate safeguards have been incorporated into the design. (W.D.M.)

The masses of the isotopes of the heaviest elements have been calculated from known decay data in the region, extended by means of decay energies calculated from closed decay-energy cycles and estimated from the systematics of alpha and beta decay energies. The absolute values of the masses are based on the mass-spectrometrically determined mass of Pb{sup 208} and a few measured neutron binding energies. The half-life systematics of alpha decay and spontaneous fission are also presented, and some predictions of the properties of as yet undiscovered nuclides are made.

Experiments were performed with 2.09% U/sup 235/-enriched uranium metal plates in a light-water-moderated and -reflected assembly. Each plate was 30 in. long, 31/8 in. wide, and 1/4 in. thick and contained 7.09 kg of uranium. In the first assemblies the plates were arranged in rows with edges adjacent, and the spacing between rows was varied from 5/8 to 1 1/8in. The optimum spacing was about 7/8 in. With the spacing between rows maintained at 7/8 in., the spacing between the edges of the plates was varied from 0 to 5/8 in. The optimum spacing between edges was 5/16 in. The minimum critical mass in these assemblies was 6.74 kg of U/sup 235/. (auth)

The economiics and physics of four schemes of pIutonium recycle in the Calder Hall type reactor are considered. The four possible schemes are: (I) to blend the Pu produced In a run with fresh naturaI U for a subsequeut run; (2) to alloy the Pu with somie diIuent metal and fabricate the alloy Into high heat- transfer elements morc like MIR or PWR-sced type elements and"spike' a subsequent load of fresh natural U elemients with these Pu elemicnts; (3) to recycle half the spent U as well as the Pu; and (4) to thke advantage of the extra reactivity gained fromi the recyeIed Pu to deerease the Iattice spacIng, thereby increasing the conversion ratio with the hope of increasirg the attaInabIe exposure. It was concluded that schcme (1) is the miost economiical. (W.D.M.)

Experimental conversions of UO/sub 3/ to UO /sub 2/ to UF/sub 4/ in batch fluidized bed pilot-scale contactor have demonstrated that conversion rates approaching those predicted from basic kinetic data are attainable. Further studies with fluidized beds in columns incorporating a very slight taper show that solids mixing with attendant product contamination is reduced by a factor of ten as a direct result of the taper. Experiments with tapered fluidlized beds made the design of continuous (as opposed to the step enrichment of a multistage contactor) countercurrent contactors practical. Design procedures, in generalized form, are presented. The procedures take into consideration heat transfer, mixing losses, reaction kinetics, and chemical equilibria. (auth)

A stagewise approach was used in a theoretical analysis of pulse columns. In the analysis the column was arbitrarily divided into discrete stages comprising that part of the column between two adjacent perforated plates. The operation of the pulse column was described mathematically using material balance equations, and a design method was derived which used two stage lines and two operating lines, one set for the pulse generator upstroke and one set for the downstroke. Assuming equilibrium contact, the effect of recycle in a pulse column was shown to cause a large decrease in the separation obtained as the pulse frequency was increased. Hold-up studies were made using isoamyl alcohol- water, and methyl isobutyl ketone water. The hold-up per cycle of the dispersed phase for both systems was found to be equal to the interstage flow per cycle of the dispersed phase. Hold-up behavior at high frequencies was different for the two systems. Extraction runs were also made using the system methyl isobutyl ketone - acetic acid-water. The effects of recycle were found to result in a drop in column separation efficiency with increased pulse frequency. It was found to be theoretically possible for a column to operate in a …

The effect of hot-worked thickness on the corrosion behavior of atmosphere-melted Zircaloy-2 is discussed. Hydrogen pickup upon etching Zircaloy- 2 Zircaloy-3, and properties of vacuum-cast Zircaloy-2 and the fabrication of special Zirccaloy shapes are presented. A hardness converison chart for annealed zirconium and zirconium alloys is included. (J.E.D.) The useful properties of the tungsten wires used in the incandescent lamp and ra dio tubes industry are ensured by adding about 1% of various ingredie (e.g., K, Na, Al, Si compounds) to the tungstic acid and producing metal powder and compressed rods. During the sintering of these rods, the additions are evapo rated to such an extact that finally the concentration of foreign atoms remains only 10/sup 5/. According to the investigations, the warm hardness values of these tungsten pieces is determined by the traces of impurities. In order to investigate the influencce of the various kinds of atoms, an apparatus was built for the determination of half-micro warm hardnesses of various kinds of tungsten metals in the temperature interval 20 to 800 deg C The tungsten wires made with additions containing Si had an average hardness H/sub V/ = 250 at 800 deg C, while the wires without such additions …

A series of reactor frequency response measurements, relating flux or power level to a reactivity input function, were made to evaluate reactor stability for different values of power parameters. These parameters included: power level, steam pressure, and control rod position. The results were extrapolated to predict EBWR stability at higher operating powers. The experimental data may also be used to evaluate the thermodynamic and hydraulic constants. (authl

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