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A 40-day uranium core canning test (10,000 lbs of high nickel AlSi) is proposed in which one canning line has only AlSi of 0.78-1.1 % Ni added as makeup; the other canning lines would be operated as usual. Besides monitoring the Ni content and other impurities in the test and control lines, attributes, variables, and destructive fuel element data would be collected and analyzed. Estimates for annual savings are given for 8, 9, and 10-line shifts per day.

This report details measurements of fission product ratios which were made an various samples of the Purex canyon exhaust filter to determine the manner and time interval in which the filter became plugged vith foreign material. Results for samples from different levels within the filter bed were compared to investigate accumulation as a function of depth. Strontium-89/strontium-90, Zr-95/Ca-137, Ru-103/Ru-106, and Ce-141/Ce. Pr-144, ratios were determined. These were compared to a constant rate model for accumulation of fission products on the filter. Observed Sr-89/Sr-90 and Zr-95/Cs-137 ratios fall within a range of values typical of normal plant operation, Specifically long-term accumulation of Hanford material irradiated at 10 MW/T to between 600 and 900 MWD/T total exposure and cooled between 120 and 200 days. Low Ru-103/Ru-106 and Ce-141/Ce, Pr-144 ratios definitely rule out rapid accumulation of short-cooled material as the build-up mechanism but are not sensitive indicators in the case of long-cooled material. Ratios did not vary significantly with sample location, indicating that accumulation age does not differ with depth within the filter.

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This report is an inventory record of materials which were received and shipped from the Purex Process during this time period. Material accounting includes uranium, uranium-235, plutonium, and other transuranics.

Figures are given.

During the January, 1964, outage at H reactor, major rear-face hardware modifications were performed and enlarged venturis were installed full reactor. These modifications significantly change the reactor hydraulic characteristics. Process Standards - Water Plant) 190-B-070, requires tripout tests be performed whenever a major change is made to either the process pumping system or the reactor hydraulic characteristics. Production Test IP-651-Al was performed on January 17, 1964, to evaluate (1) transient flow decay-characteristics associated with complete loss of BPA electrical power to 100-H area, (2) riser pressure trip settings for the ball 3X system, and (3) backup adequacy of the last-ditch coolant system. The purpose of this document is to report the numerical results of this test.

This document defines the objectives, bases, and functional requirements that shall govern the preparation of design of the coolant backup system for three remaining smaller reactors. This project will increase the reliability of the coolant backup facility at B Area by providing an independent last-ditch coolant system to B and C Reactors. The reliability of the last-ditch system for D Reactor will also be improved in that the present F and H leg of the export system will no longer be a part of the new export system.

This barely legible document contains Zn-65 and Co-60 concentrations and total dose contributions from F area HCR`s. Differentiated include tubes form full rods, tubes form half rods, and outer sheath`s.

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The results of an extensive survey of the literature and of the subsequent analysis permit the prediction of the rate of radiolytic decomposition of the water coolant. Due to the difficulty in assessing the rate of the back reactions, fundamental data from water radiation chemistry could not be applied in a straightforward manner. It proved more expedient to employ the actually observed decomposition rate data from other boiling water reactors and to extrapolate to the operating conditions of SNAP 4. By this approach, the water decomposition rate was estimated to be 5 lbs/day. To assure adequate capacity under all conditions, the catalyst bed was sized to handle twice this rate. Based on the design method of Garber and Peebles, a catalyst bed 3 inches in diameter by 12 inches long, consisting of platinum-coated alumina pellets, appears ample. Operation of the recombiner in a closed recirculatory system was analyzed. It appears that an excess of hydrogen will result as oxygen is preferentially consumed in the initial corrosion process (metal oxidation). Once a stable oxide film is established on the stainless steel surfaces and the excess hydrogen is drawn from the system, the recombiner can thereafter handle the radiolytic gases satisfactorily. (auth)

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This document is divided into: byproduct horizontal control rod system (5 reactors); high-speed scanning-effluent temperature monitoring system (KE reactor); improved reactor gas system (100-KE & KW); safety circuit system modifications (5 reactors); alternate process hot die sizing, 313 Building 300 Area; button line equipment (234-5 Building); in-tank waste solidification (3rd unit); and misc. minor equipment projects.

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