The practical application of heavy water purity determination by infrared absorption spectroscopy using standard laboratory equipment was demonstrated in connection with the operation of heavy water-moderated Special Power Excursion Reactor Test (SPERT II) Facillty at the NRTS. (auth)

A discussion of the fundamental aspects of vaporization is presented along with a discussion of evaporation within the theories of solids and gases. Suggestions are offered as to where assumptions might be introduced to describe the phenomenon more completely, and tenative definitions concerning factors which can give rise to vaporization coefficients are given. An effort is made to unify these concepts within the phenomenological framework of irreversible thermodynamics. (J.R.D.)

In order to evaluate entry into the atmosphere of an oblate (equatorial bulge) earth a standard atmosphere was used in conjunction with the standard rotating oblate spheroid. The density variation encountered in any one polar orbit around the earth will vary by about a factor of ten, due to oblateness. Therefore, the important effects on the re-entry trajectory are atmospheric density and oblateness of the earth. The SNAP configuration burn up characteristics will differ considerably between the steep (6/sup 0/) entry of the NASA Scout test and the orbital decay trajectory. However, the test can verify heat transfer rates on the actual configuration, and by proper calculation of material response, the actual decay breakup prediction can be improved.

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The economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO/sub 2/ nuclear fuels were compared. A 2.66 metric ton U/day head end portion of a plant was designed for each process and capital and operating costs were developed. For plants of this size and larger, mechanical shear-leach processing has the advantage of ~20% lower capital cost and 50% lower operating cost. Processing costs of stainless steel-jacketed UO/ sub 2/ by the Sulfex and shear-leach methods, including amortization and waste disposal but excluding solvent extraction, were .78 and 7l/kg U, respectively. Storage of stainless steel waste produced by the shear-leach method is less costly by a factor of 20 than for Sulfex. (auth)

A semiautomatic film badge system was developed to process dosimeter film faster and more reliably than the previously used manual method. The films are automatically loaded and unloaded from the badges and marked with identifying numbers, manually developed, and automatically read. The resultant information is punched into IBM cards. (auth)

Details concerning a recommended system of flow-plan symbols and drawings are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. (J.R.D.)

The core design and the fuel element concept for the high-flux Argonne Advanced Research Reactor are presented. The core is cooled and moderated by light water and utilizes beryllium as a reflector. The fuel element assembly is rhomboidal in cross section and consists of 27 plates fastened together at their edges by dovetailed locking keys, and at each end by end fittings. Each fuel plate is 40 mils thick and contains a uniform dispersion of highly enriched UO/ sub 2/ particles, up to a maximum of 37 wt%, in a matrix of sintered stainless steel powder. A 5 mil thick stainless steel cladding is metallurgically bonded to each side of the fueled matrix. (N.W.R.)

A project has been proposed and the funds allocated for the replacement of the central zone aluminum process tubes at both K Reactors with smooth bore zirconium process tubes of approximately the same outside diameter as the original tubes. Associated with this project is the problem of relieving the present graphite stack distortion in the vicinity of the process tube channels and counteracting or prereliving, at this time, the expected graphite stack distortion that, will take place over the next ten years. Such relief becomes increasingly important when it is realized that long reactor life is required for the zirconium tubes in order to justify the cost of the project. This justification is also based upon the ability to charge normal sized, self supported fuel elements during the reactor life of the tubes. Relieving the restrictions in the graphite process channels caused by stack contraction will be done by removing localized portions of the graphite from the tube blocks and trunion blocks with a guided cutting tool. This immediately brings up the question of graphite temperatures and the presently imposed maximum graphite in temperature limits. Combined coring and graphite stark distortion could result in excessive graphite temperatures or localized hot …

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In partially-ionized cesium plasmas above 10/sup 13/ ionscm/sup -3/, the plasma-broadened lines are easily measured and can be used as a simple diagnostic method for the determination of ion density, once the width versus ion density relationship is established either theoretically or experimentally. Measured line widths are presented and results are compared with theoretical widths. The profiles of various lines of the sharp, diffuse, and fundamental series lines of cesium were measured at known ion densities with a scanning monochromator on a hot-cathode parallel-geometry cesium diode. For each case, the ion density and the electron temperature were determined by measuring the intensity of the radiative recombination continuum. Line intensities gave independent measurements of temperature that were in agreement with electron temperatures, showing the existence of local thermodynamic equilibrium and providing a confirmation of ion density through the application of the Saha equation. Detailed results of line width measurements are presented for a range of plasma density from 3.2 x 10/sup 13/ to 1.6 x 10/sup 15/

A mechanical gage was designed to measure the bow over any one-foot length of long cylindrical material. The gage was used successfully for measuring bow in components of tubular fuel elements at the Savannah River Laboratory. (auth)

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<><DSN>16:009503<ABS>Included are summaries of studies of: DCX-1 operation and performance; DCX-2 design and engineering; plasma physics; vacuum arcs; ion production, acceleration, and injection; plasma theory and computations; magnetics; and vacuum system techniques. Separate abstracts were prepared for the eight sections. (B.O.G.) 9504(Faye unscannable abstract)

In order to study resonances in the {Sigma}-{pi} system, we have analyzed reactions in which a {Sigma} hyperon and two or three pions are produced in K{sup -}-p interactions at 1.22 {+-} 0.040 and 1.51 {+-} 0.050 GeV/c incident K{sup -} momentum (i. e., 1895 and 2025 MeV center-of-mass energy), using the Lawrence Radiation Laboratory's 72-in. hydrogen bubble chamber.

A study was made of the adaptation of the HAPO anion exchange process to the reprocessing of Fast Ceramic Reactor (FCR) fuel using the Idaho Small Plant Concept. It is shown that the anion exchange flowsheet meets the reprocessing objectives of the FCR case and can be adequately accommodated in the Small Plant Concept. Capacities of up to 1550 Md(e) are feasible in the Small Plant and unit reprocessing costs range from 0.14 to 0.28 mills/kwh depending on the number of reactors to be processed. (auth)

A technique is presented for liquid ammonla leaching of metallic sodium from corrosion coupons, filter elements, and sodium samples to reveal contaminants and impurities. The advantages of the method in preserving the physical form of corrosion or mass-transfer deposits are demonstrated. A possible application to the determination of trace oxygen in sodium is mentioned. (auth)

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The concept of overboring the graphite channels in an older Hanford reactor and installing oversized tubes charged with oversize fuel elements is being investigated at C reactor. Recently a column of these oversized test fuel elements exhibited three uranium cleavage (split) type failures after experiencing severe reactor flux cycling. This report presents a preliminary description of both the fuel failures and the flux cycling encountered by the reactor.

The cation exchange characteristics of several commercially available zeolites were evaluated, Equilibrium loading characteristics and exchange capacities were determined experimentally in the binary systems cesium-lithium, cesium-- sodium, cesium--potassium, cesium-Tubidium, cesium -- hydrogen, cesium-- ammonium, strontium-- magnesium, strontium-- calcium, strontium-- barium, and strontium-- hydrogen for several zeolites. Exchangeable cation fractions in the equilibrium solutions were varied from 0.2 to 0.00001, while the total normality of the system constituents was held constant. Results were plotted as equivalent fraction of the traced cation on the zeolite at equilibrium vs. the fraction of traced cation remaining in the equilibrium solution. If an influent composition is known, and falls in the system listed above, zeolite column loading may be read directly in univalent-univalent or divalent-divalent systems. However, in the strontium-sodium or strontium-- hydrogen systems, a k value must be used because squared terms appear in the equilibrium expression as follows: 2 Na- zeolite plus or minus Sr-solution in equilibrium 2 Nasolution + Sr-zeolite, or k = (Sr-zeolite)(Na-solution)/ (Na-zeolite)2(Sr-solution). The k for a given cation is a function of zeolite loading with that cation. Several column 50% loading capacities were determined to randomly test the validity of the above curves to predict column capacities, Several columns …

A subcritical fast reactor, fueled with Pu, is described. Calculations and experimental measurements of neutron flux and gamma dose rates near the bare core face are reported, as well as the core temperature increase eaused by Pu alpha and gamma heating. (auth)

The early thermal history of meteoritic matter is discussed. Clues obtained from the mineralogy of the carbonaceous chondrites are described. An attempt was made to establish the origin of the high-temperature minerals that served as the starting material for carbonaceous chondrites and the possible settings for the aqueous stage of the minerals. The occurrence of primordial noble gases in the meteorities is discussed. Chemical fractionations in the chondrites, extinct radioactivity, and general isotopic anomalies are also discussed. A series of possible events in the history of the solar system, based on the conditions discussed, is presented. (M.C.G.)

A second order form of the cylindrical P-3 equations is obtained for the case of an isotropic source. The boundary conditions and numerical method are discussed. Input preparation and operating instructions are included. (auth)