The following quarterly progress report covers the period of August 15 to November 15, 1962. It summarizes three activities of the group. The first part is the optical study of the absorption band associated with the F-center in RbCl. The second part discusses some elementary calculations of the spin-lattice relaxation times, the primary purpose of this step is to indicate the nature of the theoretical problem faced and show the large gap between the value calculated theoretically and measured experimentally. The last section includes more data on the shape and recovery of the hole in a EPR band associated with the F-center in KCl.

This document contains the results of weekly sampling of various isotope concentrations from effluent water at the 100 area at Hanford from July 1962 to February 1965. Compiled data in microcuries/milliliter are given. Each sampling records the concentrations of iodine-131, phosphorus-32, zinc-65, scandium-46, chromium-51, and cobalt-60. Records prior to October 8, 1962 also contain information on strontium-90, cesium-137, zirconium-95, ruthenium-103, ruthenium-106, and strontium-89. These last records are all from F reactor samples.

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The design of high-performance natural-circulation boiling systems requires that the behavior of the systems be characterized under transient conditions. In order to accomplish this, the time- and space-dependent continuity, energy, and momentum equations for a natural-circulation system are written. This publication presents a technique for solving the equations of a natural-circulation system. The solutions are compared with experimental results at various pressures with two geometries in boiling water systems. The solutions meet the established criteria. The analog model is useful for predicting the behavior of twophase natural-circulation systems during transients. The model accurately predicts the point at which such systems exhibit osciilatory behavior. The results were found to be sensitive to the vapor-liquid velocity ratio (slip ratio) used in the computation. The velocity ratio correlation used in the model is presented. All computations, circuits, and operating irformation necessary to duplicate the experiment are given. (auth)

The heat capacities of erbium and yttrium ethylsulfates were measured in the range 12-300 deg K. The magnetic contribution of the erbium ion was evaluated with the help of an assumption concernlng the difference in lattice contributions between the erbium and yttrium salts. The contribution agrees, to within experimental error, with the experimental energy level scheme for the /sup 4/I/ sub 15/2/ state previously published. (auth)

The results of all exchange experiments suggest that tritium produced by a contained nuclear explosion wiil be mixed with environmental water. Tritium exchange in the reaction HTO + H/sub 2/ in equilibrium HT + H/sub 2/O was catalyzed at 600 deg C by a number of oxygenated salts that occur in salt formations. Calcium sulfate was the best catalyst, with values as high as 49 and 77% with pure CaSO/sub 4/ and Drierite, respectively. in deep bed tests. Even under diffusion-controlled conditions, where reactant gases were passed over fine powders of CaSO/sub 4/, exchanges were as high as 26% for residence times of 50 sec. Sodium chloride had no effect. At high temperatures in a plasma jet, with D/sub 2/ as a stand-in for T/sub 2/, exchange was very rapid. For 90 msec residence time and a D/sub 2//H/sub 2/O feed ratio of 1.3, 53% of the water hydrogen exchanged with deuterium. (auth)

A device for purifying and recycling the helium atmosphere of two dry boxes having a combined volume of 50 ft/sup 3/ is described. Trace impurities are removed by passing the helium through a palladium-catalyst container and a molec ular sieve bed and cooling to - 195 deg C before passing through an activated charcoal bed. Flow rates of 10 scfm and purity levels are estimated. Regeneration procedures are given. Construction prints and a schematic diagram of the heliumpurification unit are shown. (H.G.G.)

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Calculations are reported relating to the uniform lattice critical experiments performed in the ZPR-VII critical assembly with both THUD and Babcock and Wilcox thoriaurania fuel and heavy water as moderator. Constants appearing in the criticality equation and material bucklings are computed for lattice pitches used. Reflector savings are calcuiated and used in conjunction with experimental critical dimensions to calcuiate geometric bucklings. Analyses are carried out for various experiments, such as measurements of U/sup 235/ and Th-- Cd ratios, water worth, and fuel-substitution experiments. Theoretical and experimental values are compared whenever possible. (auth)

The magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident are discussed. Each system may include a combination of coaxial loops, cylindrical or plane annular current sheets, and cylindrical coils of rectagular section. Working equations are listed, following an outline of theory. A discussion of errors and of means for reducing them leads to specific suggestions ior use of the method with any programmed computer. An existing comprehensive program for the IBM 7090 is described in detail. The rate of convergence of the harmonic series depends on the ratio R of the polar radius of the field point to that of the current discontinuity nearest the origin. In some cases the precision reaches 1000 parts per million even at R = 0.95, improving to 1 or 2 parts at R = 0.80. Since the origin is arbitrary, the practical range of the method often includes the whole space that is accessible to experiment. For very close approach to the windings one must resort to elliptic integrai methods or their equivalent. Alternative programs …

A three-part Fortran program for IBM 704 computation of the relative cross sections of isomers produced in nuclear reactions is described. The three subprograms compute the partial compound nucleus cross sections and the normalized initial compound nucleus spin distribution, the normalized spin distribution following particle emission, and the normalized spin distribution following gamma emission. The Fortran listing of the program and cards for a sample problem is included. (D.C.W.)

An analysis of outstanding problems still presenting difficulty with respect to understanding the quantumconversion process in photosynthesis is presented. Considerations of how some of these difficulties may be overcome are included. The dynamic process of energy conversion is considered in terms of photon absorption, electronic energy transfer, trapping in long-lived excited states, primary oxidants and reductants, and the electron transport chain leading to products representing stored chemical potential. The physical structure of the apparatus accomplishing this energy conversion is sought in the framework of the concept of the photosynthetic unit. The nature of this unit--its size, composition, arrangement and orientation of components, internal electrical and polarizability properties, and assembly and aggregation in the chloroplast--and the problems related to its determination are essential considerations in the overall approach to the understanding of the mechanism of energy conversion. (auth)

A total of twenty papers and one roundtable discussion were presented. Separate abstracts were prepared for eighteen of the papers. The papers for which no abstracts were prepared are concerned with impact energy sorption by large shipping casks, design of a Pu and enriched U shipping container, and the roundtable discussion on regulatory standards. (J.R.D.)

A nondestructive method was developed for measuring the spacings at the ends of fuel rods in completed SNAP fuel elements. A precisely aligned radiographic technique is employed to form an undistorted image on extra fine grain radiographic film. The end gap is then measured with a 20 x measuring microscope. The radiographic technique, alignment gages, and film reading methods are described for measuring gaps at the blend end and blind end of the fuel elements. The accuracy of measurements at the blend end ranges from plus or minus 0.0005 in. for spacings up to 0.010 in. to plus or minus 0.002 in. for spacings above 0.025 in. The accuracy at the blind end is about one-half that at the blend end. (auth)

Results of chemical and radiochemical analyses of Clinch River water, animal life, and sediments are presented for the period May to October 1961. Surface-water hydrology included establishment and operation of gaging stations and stream-flow studies. (R.J.S.)

A total of twenty-eight papers was presented at the meeting. Nine of these papers were previously abstracted in NSA. Separate abstracts were prepared for nineteen papers. (J.R.D.)

Two type-AUC graphite fuel elements loaded by solution impregnation to an average concentration of 0.115 g/cc of 93.13% enriched U converted to UC and UC/sub 2/ were irradiated at temperatures of about 1500 deg C to a 10.2% maximum burnup, corresponding to an irradiation level of 219 kwh/cc or 2.45 x 10/sup 19/ fissions/cc of fuel element. Post-irradiation measurements of the elements showed dimensional changes of -4.3 and -4.8% with the grain, and --0.8 to -2.5% across the grain. Weight losses were 3.2 and 5.1% for the individual elements with approximately 11% of the total U being lost from the elements. With-the- grain thermal conductivity at nominal room temperature was reduced by a factor of approximates 7 and electrical conductivities by factors of 3.4 to 8.3, also at room temperature. Impact strength appeared to be somewhat improved by irradiation. Migration of U within the element was detected by radiographic density observations but not evaluated quantitatively. As anticipated, fission product release was high. (auth)

Activities in a program to assemble and test jacketed fuel rods and multi-rod fuel rod assemblies for EBR-II are reported. Other work is reported on evaluation of the manufacturing techniques proposed for the EBR-II cycle in a sustained operation and on remotely operable equipment under production conditions. Data on fabrication and assembly of fuel rods and assemblies are included. A total of 10,781 fully inspected fuel rods were fabricated for EBR-II core by processes adaptable to remote operation. (J.R.D.)

Urania-neodymia compositions were sintered in air and in hydrogen. The compositions were studied by chemical, x ray, and differential thermal analyses. Solid solutions formed readily in air-sintered compositions in the range from 20 to 60 m/o Nd/sub 2/O/sub 3/. Solid solutions formed slowly and incompletely, up to 1650 deg C, in hydrogen-sintered compositions. There was good correlation between the differential thermal analyses and the chemical and x ray analyses. (auth)

The He atmosphere system in Argonne's Facility 350 is described in detail. The system is straightforward, employing drying and carbon towers for the removal of moisture, oxygen, and other impurities. The bulk of the 15,000 ft/ sup 3/ of He atmosphere is continuously recirculated at nearly atmospheric pressure. Purification is accomplished at 140 psig on a portion of the gas that is passed through the drying tower at room temperature and the carbon towers at -- 46 deg C (--50 deg F). The operation is continuous, requiring a minimum of maintenance and operational manpower. The He atmosphere is supplied to the glove- boxes with impurity levels below 3,000 ppm nitrogen, 1,000 ppm oxygen, and 50 ppm moisture. Such purity levels prevent oxidation and combustion of the Pu materials being processed. Experimental data concerning the adsorption of oxygen from He by activated carbon over a range of temperature and pressure conditions are reported. (auth)

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