The burns to the skin of anesthetized rats were determined for the thermal radiation pulses of a carbon arc on a hot-wet uniform when spaced 5 mm from the skin. The radiant exposures to cause burns resulting in eschar were tion pulses corresponding to 250, 1000, 2900, and 10,000 kiloton detonations, respectively. The threshold lesions were caused by volatile products not associated with ignition. The associated temperatures were recorded. (auth)

This code finds inelastic cross-section matrix elements (transfer matrix) for hot monatomic moderator for multigroup calculations by numeric- analytic double integration of Cohen's formula. Several approximations to the actual neutron density ean be used as weight functions over the velocities of the initial groups. Modified and supplemented results are presented on binary cards and/or tape for direct input into the Argonne Transport Theory Codes or the SNG Code, or for offline output. (auth)

The process water pumping system for the K-reactors consists of six parallel sets of two series-connected pumps. A BPA outage could sever the power to all pumps. It is of major concern to known how the reactor flow decays with time following the power severance. The following analysis gives the general solution of this problem without recourse to the assumptions which have been used heretofore. The solution of the decay problem was programmed on the IBM 709. The program will give the flow transient for two series-connected pumps arbitrary physical characteristics, initial conditions, system and supply curves. It will give the decay characteristics for loss of power to either or both pumps. A full description of the program and its output is given in the Appendix.

The neutron flux distributions in an EGCR cell containing seven and clusters of 2.0 and 2.6a enriched uranium odde were obtained by using a one- velocity, one-dimensional P-3 solution to the neutron transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experiments and calculated distributions. Flux traverses in the outer rod perpendicular to diameter of the cluster are also presented. (auth)

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A method is presented for calculating thermal neutron fluxes in the primary shields of reactor systems which eliminates reliance on mock-up experimental data. A multigroup P/sub 1/ approach is ernployed with the spatial dependence of the neutron sttenuation adjusted through use of a point source attenuation kernel for a homogeneous hydrogenous medium. Comparison of calculation with experiment is presentad. (auth)

Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy. (auth)

A simplified model for solids deposition in the pot calcination of waste was analyzed, and numerical calculations were made. In long calcination pots of 10 to 12 in. diameter, calcination times should not exceed 24 hours and might be as low as three hours if the pot is kept full. If the pots are fed at a constant rate, the cake might form with a steady state V'' when viewed in vertical section which would progress from bottom to top. Cake deposition rates appear to be independent of pot radius. Several advantages to using larger diameter pots are discussed. (auth)

Calculations are given for eighteen stainless steel clad helium bonded specimens of UO/sub 2/-ThO/sub 2/ containing normal U to be placed in 6 holes in a holder in a position of the ORR not to exceed a peak unperturbed flux of 4 x 10/ sup 14/ n/ cm/sup 2//sec and irradiated to a peak nvt of 1.96 x 10/sup 21/

The speed range of the Sandia 12-by-12-inch transonic wind tunnel was recently increased from Mach 1.35 to Mach 2.0 by the installation of interchangeable fixed Mach 2 nozzle blocks. The installed blocks are shown. (auth)

Studies were made to determine the actual surface temperature of OMRE fuel elements if the thermocouple were not present. Chromel-alumel thermocouples are being attached to the fuel plate cladding of Type 304 stainless steel. These wires are in contact with the coolant stream. Heat transfer from the thermocouple junction, by conduction along the lead-wires and by forced convection to the coolant, produces a lowering of the surface temperature in the region of the junction which results in an error in surface temperature measurement. (W.L.H.)

A preliminary investigation was made of techniques and materials for canning graphite to protect it for use at high temperatures in a nitrogen--oxygen atmosphere. Fabrication techniques for cladding bare and copper--plated graphite cores either in Type 316 stainless steel or Inconel X were developed. Specimens of the various combinations of core and cladding materials were subjected to simulatedservice conditions and evaluated. In all cases the Type 316 stainless steel-clad specimens failed by carburization and subsequent oxidation in relatively short periods of time. Although considerable trouble was experienced with rupture in the vicinity of the cladding welds during thermal cycling of the Inconel X-clad specimens, this material appeared to be satisfactory in other respects and is considered promising. A specimen of silicon-coated graphite eiad with Type 316 stainless steel was tested by heat treating for 624 hr at 1800 deg F. The silicon coating alloyed with the cladding material, formed a high-silicon diifusion zone, but prevented carburization of the stainless steel. (auth)

A brief survey of decarboxylation reactions and carboxylation reactions that are known or presumed in biological systems will be presented. While a considerable number of amino acid decarboxylations are known, their mechanisms will not be included in the present discussion but will be reserved for a later paper in the symposium. The remaining decarboxylation reactions may be subdivided into oxidative and nonoxidative decarboxylations. In most cases, these reactions are practically irreversible except when coupled with suitable energy-yielding systems. The carboxylation reactions which are useful in the formation of carbon-carbon bonds in biological systems seem to fall into two or three groups: those which exhibit an apparent ATP requirement, and those which exhibit a reduced pyridine nucleotide requirement, and those which exhibit no apparent ATP requirement. Of the first group at least four cases, and possibly six or seven, are known, and one interpretation of them involves the preliminary formation of 'active' carbon dioxide, generally in the form of a carbonic acid-phosphoric acid anhydride. Those exhibiting no apparent ATP requirement seem to be susceptible to classifications as enol carboxylations in which the energy level of the substrate compound is high, rather than that of the carbon dioxide. There appear to be …

The manufacture of fuel blanks used in the fabrication of fuel elements for the Argonne Low Power Reactor is described. The thin, plate-type elements contain a wrought aluminum-base core alloy with a nominal composition of 17.5 wt.% enriched uranium, 2.0 wt.% nickel, and 0.5 wt.% iron, clad with an aluminum-- nickel alloy. The fuel ele ments were fabricated by a picture-frame technique, employing elemental silicon bonding and followed by hot and cold rolling to size. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed. A description of the nondestructive testing method and an evaluation of the manufacturing processes are given. (auth)

The casting of shapes of uranium--molybdenum metal of varying sizes and thicknesses from a molten charge has been successfally accomplished with specificially designed graphite distributors and molds. Solid cylinders, hollow cylinders, and flat plate shapes were cast in gang molds. As many as 35 solid cylinders have been cast simultaneously. All castings had smooth surfaces, and solid shapes were cast to 0.006-in. tolerance on all dimensions except length. (auth)

Casting a U shield for a kilocurie Co/sup 60/ source is described. The melting equipment is described, and data on the castings are tabulated. Examination of the casting revealed no large blow holes or cracks, and the method was considered adequate. (J.R.D.)

Centrifugal-casting techniques were investigated as a method of producing hollow cylindrical extrusion billets of aluminum-35 wt.% uranium. Among the variables evaluated were melt temperature, mold and pouring-spout configurations, mold speed, and method of pouring. With the equipment employed it was found that the best castings were produced utilizing a pouring temperature of 2400 ction prod- , a heavy-walled steel cylinder rotating between 700 and 900 rpm for the mold and a bottom-pouring technique employing a retractable pouring spout. Sound, nonporous billets 26 in. long and 5 in. in diameter were produced with a yield after machining of over 75% of the original charge. The major losses occurred in the pouring spout-and-cup asserably. This loss is relatively unaffected by the casting length; and, therefore, castings of greater length than 26 in. should result in even greater recoveries. (auth)

Several decisions regarding basic project philosophy must be made in order to proceed with scope design and the preparation of equipment procurement specifcations. The purpose of this document is to present as much pertinent data as possible to allow the project representatives to become familiar with the problems involved. A meeting of Representatives is planned for the near future after receipt of project authorization to discuss the scope of this project and its relationship to CG-775. Emergency flow requirements of the K reactors for planned future power levels is approximately 32,000 gpm within 68 sec. A detailed study of the existing high-pressure cross-tie line reveals that a duplicate cross-tie line and five low lift pump operation would be required to provide this flow. The existing emergency generation capacity is not adequate to supply five low lift pumps and all other necessary emergency electrical loads. A possible solution to adequate emergency flows is to connect the proposed steam turbine pump directly to the risers and to consider the turbine pump as the last ditch system. If it is determined that this does not meet the criteria of separate systems, then an alternate solution must be found.

Surface active materials in aluminum nitrate-nitric acid fuel reprocessing solutions were characterized. Polymerized silica, zirconium- modified silica and soluble dibutyl phosphate species were found to contribute to stable emulsion formation. These surfactants were reduced in effectiveness by added acid. (auth)

The products from the flssion of U induced by charged particles were studied in a mass spectrometer. Both U/sup 238/ and U/sup 235/ were bombarded with 45.7- and 24-Mev helium ions, and U/sup 238/ was also bombarded with 730-Mev protons and 100-Mev carbon ions. Tbe total chain-yields in the region of the rare-earth elemerts (mass 140 to mass 155) for most of the above bombardments and a thermal-neutron bombardment of U/sup 235/ were studied by using the isotopicdilution technique. Independent yields were measured for all the above bombardnnents for several shielded nuclides. (auth)

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Chemical-Metallurgical Processing. A direct-cycle Pyrometallurgical fuel-reprocessing plant is being designed in conjunction with the EBR-II reactor. Studies were continued on processing of melt-refining residues (crucible skull material). Skull oxlde reductions in Mg--Cd solutions are in progress. Methods of isolation of Pu from EBR-II bIanket material are being examined. Cadmium contafntng ~2% U and 0.2% Mg is betng circulated at 550 deg C by an electromagnetic pump. Solubilities of Ru, Ce, and La in Cd were measured at temperatures from 325 to 625 deg C; the solubility of U fn Zn was measured at temperatures from 425 to 800 deg . The high-Cd covers of the termary systems Cd-- U--Zn amd Cd--U-- Mg were investigated. Sixteen colorimetric combustions in oxygen were completed with natural MoS/sub 2/. Eight successful colorimetric combustions of Mo in F/sub 2/ were completed. Fuel Cycle Application of Volatility and Fluidization Techniques. Studies on the rates of fluorination of UO/sub 2/, as ft would appear in irradiated fuels, are in progress. Equilibrium constants are being obtained at various temperatures for the dissociation reaction of PuF/sub 6/ to F/sub 2/ and PuF/sub 4/. A systematic study of the reaction of Ni with F/sub 2/ is in progress as a …

4 -Metallurgical Processing. A direct-cycle fuel reprocessing plant is being designed for pyrometaliurgical processing of discharged power reactor fuel elements. Irradiation tests on cerium-bearing glass samples for shielding windows revealed that the optimum cerium content is less than the nominal amount originally specified. The light output of gammairadiated mercury vapor lamps was determined to be about 55% of original after an exposure of 1.1 x 10/sup 9/ rads. Analyses of the composition of 30 ten-kilogram ingots of natural U-5% fissium alloy prepared in the melt-refining furnace indicate that not all of the added Zr and Mo went into solution. Irradiation tests have shown that natural rubber formulated with an antioxidant (Antiox 4010) is satisfactory for cable insulation at radiation levels to 2 x 10/sup 8/ rads. Four 2-kilogram scale runs were made to study the meltrefining characteristics of high Pu (20%) -- U --flssium alloys. A further investigation was made of the possible Zr contamination of molten U and its Ce alloy resulting from prolonged holding at 1400 deg C in stabilized ZrO/sub 2/ crucibles. Experiments at 1700 deg C showed considerable evolution of CO as a result of reaction of ZrO/sub 2/ with graphite. Reduction of oxide coatings on …

Fluoride Volatilization Separations Process. Work has continued on the development of fluoride volatilization processes for recovery of U and Pu from spent power-reactor fuels. Results are reported on the fluorination rates of U and Pu oxides and fluorides. The conversion rate of UO/sub 2/F/sub 2/ to UF/sub 6/ by elemental fluorine was determined as a function of temperature. Uranium trioxide is fiuorinated at a slower rate than the other U compounds investigated. On exposure to fluorine PuO/sub 2/ appears to form the PuF/sub 4/, which, in turn, is converted to PuF/sub 6/. The product of the thermal deconmposition ofPuF/sub 6/ is PuF/sub 4/. The fluorination of Ni at 600 to 800 C produces films of a higher density than that of crystalline NiF/sub 2/. Flourination studies on Ti, Pt, Au, and Ag indicated that none of these netals is suitable for use with fluorine at temperatures much above 100 C. Development work continued on a high-temperature fusedsalt process for the recovery of enriched U from Zrdissolver-hydrofluornator made of graphite is nearly Reactor (LMFR) core fluid by a floride volatility process is being investigated. Fluidization Studies. Investigaition of the effect of process variables on the fluidion steps of the ADF d …