The objective of the test discussed in this report is to verify further the corrosion rate of irradiated tubular fuel elements under conditions of high specific power and central core temperatures. The fuel will be the inner component of an NPR fuel element assembly. A proposal to charge two tubular fuel elements into the GEH-P7 Loop has been made. The upper fuel element of the two has been irradiated to 1660 MWD/T in a Hanford reactor. A hydraulic cylinder will be attached to the upper fuel element. The hydraulic cylinder will be used to move a chisel along the outer surface of the upper fuel element and shear off a cap which has been welded over a hole through the cladding. The lower fuel element of the two will be used to add heat to the loop so that the desired loop water temperatures can be maintained.

This report provides some temperature and swelling data on Zircaloy-2 clad, coextruded fuel elements irradiated in the KER loops and in the GEH-3 {times} 3P7 loop at the ETR. Data on both rod cluster fuel elements and tubular fuel elements are included. Density changes, where density measurements were made, have also been included. These data are preliminary and are subject to change.

This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.

A multiple controller system for a single process is formulated in block diagram form. It is shown that for the general case of n controllers and one type of cross coupling, the system equations can be reduced to the standard forms of servomechanism theory. The effects of failure in individual controllers are examined, and it is demonstrated that the system shows considerable promise for both reliability and maintenance without process interruption.

A cross section tape has been prepared containing data for elements of most interest for aqueous homogeneous reactor multigroup diffusion calculations involving combinations of 150, 200, 240, 260, and 280°C temperatures. This tape permits multigroup analysis of a reactor in which two or more regions are at different temperatures.