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.

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.

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

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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 .