This document provides a summary of facilities, both proposed and constructed, and programs of the Hanford Atomic Products Operation. Budgets, by program, are also provided. (FI)

This report addresses the constant-pressure leak rate gage.

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Property changes in polycrystalline graphite resulting from reactor irradiations at temperatures up to 185 deg C and over a range of exposures up to 1135 Mwd/ CT have been determined. Changes in stored energy, thermal conductivity, sample length, and C/sub O/ interlayer crystallite spacing are markedly decreased as exposure temperature is increased. Electrical resistivity changes are also less at higher exposure temperatures, but this property change does not depend as strongly on temperature as the others. Isothermal annealing studies of C/sub O/ changes were conducted on a number of irradiated samples. The data were analyzed assuming a large number of processes distributed in activation energy. The results are summarized in activation energy spectra in which the distribution of C/sub O/ damage is given as a function of the activation energy required for annealing. It is found that not only does a higher exposure temperature decrease the total amount of property change, but also the distributlon of damage accumulated is considerably different. Results are discussed in terms of the radiation damage model suggested by Hennig and Hove. This model is compatible with the experimental results presented. (auth)

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Design criteria and operating experience with the aluminum oxide bearing and journal combination as installed in canned rotor pumps in in-pile loops are described. No pump failures occurred in 8 pumps with A1/sub 2/0/sub 3/ bearings over a cumulative period of l0,000 hours due to wear or corrosion. Five failures due to slippage and/or electrical breakdown of the stator insulation are reported. (T.R.H.)

Review of ThO/sub 2/ caking and sphere forming experiences in the 200 and 100 gpm loops shows that cakes and spheres always formed in the first 100 hours of the run or did not form at all, suggesting that processes in addition to oxide particle degradation were present. Many ThO/sub 2/ circulation tests in which no major difficulties were experienced suggest that preparation of oxides suitable for reactor use may have been accomplished, at least insofar as the caking problem is concerned. Further research is required to distinguish between oxide preparations. Evaluation of ThO/sub 2/ batches by cake resuspension index'' studies are described. A qualitative indication of the caking tendency of various batches of ThO/sub 2/ is given. Observations of ThO/sub 2/ sphere growth in stirred systems at atmospheric pressure indicate that added electrolytes have a strong influence. The results of ThO/sub 2/ cake disintegration tests are reviewed. A cake disintegration method has been used successfully twice to remove hard cake from inaccessible points in loops. The proposed program for caking studies in the 30 gpm loop, which is under construction, is outlined. The potential usefulness of several avenues for investigation of ThO/sub 2/ surface chemistry is indicated and the …

Although the Born-von Karman treatment of the dynamics of crystal lattices is superior to that of Debye, the conABSTRACTS tinuum model of Debye is more amenable to computation; therefore the Debye treatment is used to obtain frequencies at a maximum energy. From the classic Hamiltonian of the solid, quantization is carried out by the Schroedinger method. The thermodymamic functions are obtained, and the mean square displacement is derived. (J.S.R.)

A methed is descrihed for the treatment of radioactive neutralized nitric acid waste solutions. The process consists of electrolysis of sodium nitrate solutions and recycle the caustic formed to neutralize incoming nitric acid ate. Removal of a large fraction of the bulk inert substances by this method allows greater reductions in waste volume than conventional treatment by evaporation alone. Process chemistry studies show that a large fraction of the nitrate ion in alkaline solution can be electrolytically reduced to gaseous nitrogen reduction products at reasonable current efficiencies. Process engineering studies have resulted in the development of a prediction equation for the design of electrolysis cells used in the process. Pilot plant studies using cold'' nitric acid waste have demonstrated the feasibility of the electrolytic recycle methed. A preliminary cost estimate was performed which iadicates a cost of from 75 to 95 per initial gallon of waste processed. Basis for this estimate is a conceptual design of a plant capable of handling the highlevel waste produced in reprocessing one ton of uranium metal per day. These costs are considered reasonable in a nuclear power economy, and indications are that ultimate disposal of the concentrated waste in clay may be possible. (auth)