Methods are presented for determining the electric power requirements of a given communications mission in terms of mission and orbit parameters. Analyses were made of possible applications of available and projected space auxiliary power units in these satellites. The satellitc as a communication node is discussed. Example calculations are given. (M.C.G.)

Abstract: An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres.

"An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).

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Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.

From abstract: A preliminary study has been made of a direct access, streamlined process for the rapid fabrication of fuel using uranium-233.

This report describes laboratory-scale studies made to evaluate the feasibility of using uranium(IV)-hydrazine instead of ferrous sulfamate-sulfamic acid as the partitioning agent in the Hanford Atomic Products Operation Purex separations plant. Iron(II), in combination with sulfamic acid as a holding reductant, has been used very successfully for many years as a plutonium reductant in solvent extraction separation processes for irradiated nuclear fuels. However, the iron remains in the radioactive wastes produced in the separation processes. Its presence in these wastes accelerates corrosion of waste concentration equipment, complicates treatment of the waste for by-product recovery and adds to the total quantity of contaminated salts which must be stored. Much effort has gone into searches for plutonium reductans which would not have the disadvantages associated with iron(II). Uranium(IV) has been proposed since, having acted as reductant, it is extracted along with uranium from the irradiated fuels and does in solvent extraction separations processes have involved mixer-settler contactors. The HAPO Purex plant has pulsed-column contactors. This difference, plus certain problems due to the particular flowsheet conditions used, required that additional laboratory studies be made to determine the feasibility of using uranium(IV) in the HAPO Purex plant.

8 7 6 2 ; 7 4 7 6 : 7 8 : : ; half life of 3.781 plus or minus 0.010 years based on calorimetric measuiements. The calorimetric assay of the sample will be continued ior several years to decrease the probable error. The decay scheme for /sup 209/Po--/sup 209/Po/ isitopic mixtures is being determined. The gamma spectrum is being studied using two sources of different isotopic composition. Definite peaks were established at 76, 260, 300, 575, and 9l0 kev. Various multiple coincidence experiments indicated that the 300- and 575-kev photons and the 76-kev x-ray are in triple coincidence. Relative intensities of the various gamma rays from the two different sources indicated that the 575-kev photon is associated with /sup 208/ Po decay, while the 260- and 910-kev states are attributed to /sup 209/Po. A theoretical estimate of the partial alpha half life for /sup 208/Po decay to the 2+ level in /sup 204/Pb (at 0.899 Mev) was made. This value (2.5 x 10/sup 6/ years) was determined graphically by extrapolation to an alpha particle energy of 4.2l1 Mev. /sup 209/Po--/sup 2o9/Po sources are being prepared for the investigation of the internal conversion electron spectra of these isotopes. …

Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.

Research on a welding process for closing the ends of pathfinder fuel elements is reported. Optimum parameters for certain variables (amperage, weld travel, preheat, etc.) affecting weld quality were determined, and two modified end cap designs were investigated and found to reduce weld sensitivity to certain variables. Use of chills on the fuel tube greatly improved weld puddie geometry and microstructure. Optimum weld parameters for rods containing UO/sub 2/ fuel were experimentally established. (D.C.W.)

A method is described for obtaining an approximate solution to the equations describing a nucleon-meson cascade by using the angular dependence of the secondary particle production kernels as a perturbation. The usefulness of the method lies in the fact that in a slab geometry the equations that must be solved numerically are essentially the same as those that are used in the straight-ahead approximation and have been solved previously. (auth)

Declassified 27 Nov 1973. Information is presented concerning Tory-2C operations and testing; reactor kinetics; control system and instrumentation; and physical properties of ceramic materials. (DCC)

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This purpose of this test is to acquire data to support further studies aimed at determining whether a normal column of I&E enriched fuel elements or a normal column of natural fuel elements can be flushed from a process tube with the crossheader valved down to shutdown position if the front riser pressure is raised to normal operation pressure.

The water plants and associated steam back-up facilities which supply coolant to Hanford`s eight production reactors are large and vital facilities. Their reliability is essential to the safety and continuity of reactor operation. Their output and efficiency are important to reactor productivity and to the unit cost of plutonium and other irradiation products. In the fiscal year just ended, the cost of operating the reactor water and steam plants was $16,000,000, which represented a major fraction (37%) of the total irradiation cost for the same period. Substantial improvements in water plant capacity and operating economy over an extended period are reflected in this operating cost figure. The purpose of this report is to highlight the capacity increases and cost reductions achieved during the five fiscal years 1958 through 1962.

Results of studies concerning the asymmetric/symmetric ratio for fission induced by neutrons of energies corresponding to various fission resonances are presented. These studies were carried out primarily with monoenergetic neutrons at 1.8, 2.3, and 4.3 ev. The fission ratios in the low-energy resonance region was found to change from resonance to resonance, and the ratios appear to fall into symmetry classes each of which has a characteristic peak-to-valley mass yield ratio. It appears that a spin dependence is involved in the mass distribution as predicted by the Bohr model. The exact nature of this dependence is not clearly understood. (J.R.D.)

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Calculations of the photonuclear giant resonance according to the Wilkinson model are presented in this report. In this model the giant resonance in the cross section for absorption of gamma rays by nuclei is ascribed to the excitation of large numbers of nucleons in closed shells. The model generally predicts correctly the integrated cross section for the giant resonance, bu the resonance energy is too low. Results are presented in a series of tables and formulas so that the integrated cross section may be calculated for any given nucleus.

Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of water at 200 degree F, 31% higher than predicted, part of which was due to presence of instrument leads. Element to element flow distribution varied approximately +-8% from pass average. Channel-to-channel stationary element flow distribution varied approximately +-10% from element average and control rod flow distribution varied from +-8.9% to +-6.4 and -11.6% depending upon rod locations. These variations exceed the original goals of a +-10% and +-12% combined deviation for stationary and control rod elements respectively, but are satisfactory in relation to thermal design. There was no indication of unsatisfactory structural performance of any components under hydrodynamic loadings up to 130% of design values. The test program was terminated after determining flow distribution in the reference core design, omitting any work on …

Spectroscopic observations were made of the flow field behind a cylindrical hypersonic wave front resulting from an imploding electrical dischange into an initially low pressure quiescert gas. Sub-microsecond resolved spectra were obtained by use of a quartz prism monochromatorphotomultiplier detector system with photographic recording of an oscilloscope displayed output signal. Electrically produced plasma rings were established in detonabie as well as non-reactive gases. Strong indications were observed that exothermic reactions, as evidenced by H/sub 2/O emission, proceed in H/sub 2/ + 1/2 O/sub 2/ reactant mixtures within less than one microsecond under certain initial low pressure conditions. A reaction threshold at 1 mm Hg pressure was found for the particular reaction vessel used. Timeintegrated spectrometer photos support the conclusions reached with the transient spectra analysis equipment. (auth)

This report itemizes the irradiations performed by Testing for Battelle-Northwest Laboratories. It lists the material being irradiated, awaiting disposition and material shipped during the report period.