One source of the parent materials which are converted into the radioisotopes in reactor effluent is the impurity content of Columbia River water. It has been demonstrated that as the efficiency of removal of the radioisotope parent materials increases, the amount of radioisotopes in the reactor effluent decreases. An example of this is the activity reduction which results from the use of high alum feed. In order to determine whether effluent activity would be influenced by the length of filter run, a half-plant test was initiated at DR Reactor on September 28, 1964, under the authorization of Production Test IP-719. This report presents the results of the test. The water treatment plant at DR Reactor was operated for a three-month period with half the filters on a seven-hour filter cycle and the other half on a 5.25 hour filter cycle. The shorter filter cycle did not significantly reduce either the filtered water turbidity or the P{sup 32} and As{sup 76} concentration in the reactor effluent. It can be concluded that in the range investigated effluent activity is not influenced by the length of filter cycle as long as breakthrough is avoided.

This report details activities of the Chemical Processing Department during the month of January 1965.

The Purex Processing Measurements Quality Control Program was designed to provide for orderly accumulation of measurements data suitable for statistical evaluation and to identify those elements of a measurement which, if improved, would result in significant reduction in overall measurement variation. This report gives an analysis of the audit data obtained at four transfer stations: L9 plutonium product loadout, K6 uranium product to storage, F15 salt waste to F16 and D5 dissolved feed to process. Estimates of variation caused by analytical, sampling and volume or weight instrumentation were computed and combined to give variation associated with a single batch transfer. Procedures for collection of future data that are more suitable for statistical evaluation are suggested. Methods used to compute random and fixed variation estimates are discussed.

This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of material undergoing irradiation awaiting dispositions material shipped during the months and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, ``Status Report Equations.`` The integrated exposure reported is the average exposure received by the surrounding uranium columns. Conversion to exposure received by the sample is left to the customer.

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The purpose of this memorandum is to firm up requests for uranium oxide fuel elements. This first priority is to have two fuel columns fabricated for irradiation testing.

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The purpose of this document is to outline the proposed implementation of engineering program results to remedy the major horizontal control rod (HCR) problems at Hanford production reactors. K and C Reactors currently use a water cooled, round, aluminum control rod packed with boron carbide powder, B and D Reactors use a water cooled, flat, aluminum rod made up of sintered boron carbide-aluminum rings strung on three cooling tubes, all of which is encased in an outer aluminum shell. The nature of the problems -- progressing toward a limiting condition at a predictable rate -- lends itself well to a stepwise or ``as needed`` approach in applying a solution. Such an approach offers the dual benefits of realizing maximum reliable usage from each piece of equipment and of distributing the renovation costs over several years time. The specific program proposed herein emphasizes the immediate application phase.

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This report includes recommendations for improving the method of analysis of a sodium-water reaction in the Prototype and changing the structural design to improve the ability of the unit to withstand such a reaction.

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This report, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

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