Data report including the financial statements of several Sugarland companies, such as Foster Farms, Inc., Sugarland Industries, Inc., Belknap Realty Company, Sugarland Motor Company, Sugarland Telephone Company, and Sugarland Truck Lines.

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Quarterly report regarding the activities of the Saxton Plutonium Program, the purpose of which is gathering information and analyzing performance through design, fabrication, and operation of plutonium enriched fuel in a pressurized water reactor system in the Saxton Reactor.

This report summarizes the results of the fifth of a series of tests completed in the A-11 test program.

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A Third Party inspection of the reactor work platforms was conducted by representatives of the Travelers Insurance Company in 1958. An inspection report submitted by these representatives described hazardous conditions noted and presented a series of recommendations to improve the operational safety of the systems. Project CGI-960, ``C`` & ``D`` Work Platform Safety Improvements -- All Reactors, vas initiated to modify the platforms in compliance with the Third Party recommendations. The American Standard Safety Code for Elevators Dumbwaiters and Escalators (A-17.1) is used as a guide by the Third Party in formulating their recommendations. This code is used because there is no other applicable code for this type of equipment. While the work platforms do not and in some cases can not comply with this code because of operational use, every effort is made to comply with the intent of the code.

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The present study was undertaken for the purpose of determining the feasibility, establishing the required development program, and estimating the cost of a turbocirculator to provide the pumping power for a 1000-Mw(e) high-temperature gas-cooled reactor power plant as part of the TARGET program. This necessitated preliminary design of the turbocirculator in conjunction with the reactor power plant as well as the investigation of methods for the optimization of the turbocirculator and for its development. This study was carried out in sufficient detail to fix the methods required to resolve the problems that would be encountered during the course of a prototype program resulting in a turbocirculator for the TARGET power plant.

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To provide the NERVA test program with a temperature measurement system of sufficient accuracy to satify present and future requirements, a cryogenic temperature measuring system was designed and developed employing a platinum resistance thermometer (RTT) as the sensor.

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The decontamination cycle (HA) at Purex has occasionally responded favorably to additions of waste rework material. The effect, exhibited in increased extraction of plutonium and improved decontamination from fission products has become known as the ``Tonic effect.`` Efforts to find the agent or agents in waste rework which are responsible for this effect have not been successful. Workers at ORNL, principally C. A. Blake, found that various materials decreased the distribution ratios of zirconium-niobium ruthenium activity. This work covered oximes, ketones, and oxalic acid in the Purex HA system. Their work ended with the conclusion that oxalic acid was the most effective of all agents tested. This paper describes the work by Separations Chemistry Laboratory designed to test these and other additives in the HA system at Purex.

This report describes a study which was made to determine possible changes in mixer placement at H reactor because of the change from an enriched core load to a natural load and to evaluate movement of metal charges 8 inches downstream. Also studied was the effect of short charging on tube life and mixer position. Special consideration was given to the fact that H reactor will shut down in approximately seven months.

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This document outlines the Westinghouse Astronuclear Laboratory (WANL) specifications and procedures for acceptance testing of differential and absolute pressure transducers. All pressure transducers used for reactor instrumentation shall meet the requirements of this specification before being accepted .

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This report covers the development of a tie plate to capsule weld. This work was done in the Westinghouse Headquarters Manufacturing Metals Joining Laboratory.

This interim report details the irradiation testing of co-product fuel-target assemblies in KER loops 3 and 4 which was authorized by PT-IP-645-D. The purpose was to demonstrate and characterize the simultaneous generation of plutonium and tritium during the irradiation of simulated N-Reactor co-product assemblies. Thirteen assemblies, each consisting of a 1.25% enriched outer fuel or driver tube and an inner, coaxial, lithium bearing target rod, were loaded in KER-3 and irradiated to approximately to approximately 1300 MWD/T tube average at N-Reactor conditions. One of the important aspects of the test was the fuel swelling performance in the large, tubular, enriched driver elements. This report describes the fuel swelling behavior of the driver elements.

Production Test IP-544-A authorized the irradiation testing of coextruded Zr-2 jacketed, single tube, thick walled, 1.6 percent enriched tubular elements (KSE-5`s) in KER loops 1 and 2 to evaluate swelling behavior at high uranium temperatures. This PT was intended to permit the evaluation of uranium swelling at N-reactor environmental conditions but at considerably higher uranium temperatures than those occurring in N-reactor fuel. Evaluation of the fuel performances at the authorized maximum fuel temperatures in the 550--600 C temperature range is essential in the design and analysis of single tube fuel elements for use in N-reactor. The test was subsequently supplemented to authorize the irradiation of uranium fuel containing up to 3000 ppm alloying agents for the evaluation of swelling behavior at the high uranium temperatures. This report describes the swelling behavior of a charge of 8 KSE-5 fuel elements irradiated in KER loop 1 to appproximately 2500 MWD/T as Test K-1-22. KER Test K-1-22 is similar (except for exposure level) to KER Test K-2-21 in which a charge of 8 KSE-5 fuel elements were irradiated to 1500 MWD/T. In both tests the charges consisted of 4 KSE-5`s containing uranium with low iron and silicon additions (N-reactor fuel composition) and 4 …

This report discusses the irradiation testing of thick-walled single-tube, 1.6% enriched test elements (KSE-5`s) in KER loops 1 and 2 to evaluate swelling behavior of uranium at high temperatures. Test charge K-2-21 consisted of four KSE-5`s containing uranium with 400 ppm iron and 800 ppm aluminum. The object of the test irradiation was to establish the swelling performance of the fuel containing the iron-aluminum additions using the N-fuel composition as a reference fuel. This latter fuel has shown good high temperature performance in the British high-temperature gas-cooled reactors, but has not previously been evaluated at ``high`` specific powers in a high-temperature pressurized-water reactor environment.

This document outlines the Westinghouse Astronuclear Laboratory (WANL) specification and procedures for acceptance testing of accelerometers. All accelerometers that are to be used for reactor instrumentation shall meet the requirements of this specifications before being accepted.

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