The meetings were held on December 6 and 7, 1965 in the 325 Building conference room at PNL. The objectives of the meetings were: (1) To review the status of the ceramic coproduct target element fabrication technology and the subsequent extraction processing technology of irradiated elements as developed at PNL. (2) To discuss the feasibility of performing extraction studies of irradiated coproduct target elements at the SRL pilot plant facilities in demonstrating the capability of coproduct production in N-Reactor. (3) To identify potential problem areas that could arise when the laboratory scale extraction process would be performed on a pilot plant scale in the existing SRL facility.

The design of a Phase II dummy hydraulic core for the CSE reactor simulator is described. The core will be a scale model having features typical of PWR or BWR reactor cores, and will include control rods and associated support mechanisms, fuel elements, a thermal shield, top and bottom core guide and support plates, and flow baffles. The core and simulator vessel will be instrumented to provide measurement of temperature, static and differential pressures, forces on core components, and rarefaction wave pressures during high temperature, high pressure blowdown studies.

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A knowledge of the fuel temperature transient following a reactor flow-loss accident is important in reactor confinement studies, since the rate an time of fission product release depend upon this transient. Fuel melting times presented by Ekern, Muraoka, and Zaloudek have been used in past confinement studies. These fuel melting times were based on the solid fuel element design, and the temperature transients were not presented. Furthermore, improved fission product decay heat data and reactor scram transients are now available. Therefore, the ALOC computer code was developed to calculate the available. Therefore, the ALOC computer code was developed to calculate the fuel temperature transient following an accidental loss of coolant. This report presents fuel temperature transients for assumed accidents as calculated by this code. Operating instructions for the ALOC code are given in the appendix.

The report is about central argument against capital punishment are summarized.

It is the purpose of this report to present data obtained from the routine reactor effluent radioactivity monitoring program as well as the results obtained from the research and development program directed toward the reduction of effluent radioactivity.

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This document, dated May 3, 1966, presents data from the zirconium tube sample evaluation program at the Hanford Reservation. Data presented includes: (1) operating history, (2) flow characteristics, (3) time in core, and (4) average temperature for numerous samples. The document consists entirely of data.