This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

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.

The program is designed to use the Richland reactors to increase the national production of Pu-238 in as efficient and economical a manner as practicable while giving attention to any short-term market requirements for Pu-238.

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 …

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Variables affecting the texture and grain size of uranium during beta treatment are summarized. The study of the effect of time and temperature in the beta phase on the growth index (G3) and grain size of the final alpha product is tentatively believed to show that higher beta temperatures for short times (up to about seven minutes) tend to promote slightly more negative growth indices and that higher beta temperatures give rise to somewhat finer grain sizes. Results of studies of both Jominy end-quenched bars and several full-sized rods and tubes quenched by total immersion showed that large thermal gradients promoted negative growth indices and produced grains somewhat elongated in the direction of the thermal gradient. The effects of endcooling in full-sized pieces quenched by total immersion in cold water showed that the axial growth index is negative up to distances from the end of about half the wall thickness of tubes and about half the radial dimension of rods. The grain refinement penetrates to a lesser distance from the ends. In the radial direction the growth index for these same pieces is largely negative to a distance below the outer diameter of about midwall in two tubes studied. In …

Values of the distance of closest approach, the centerof-mass scattering angle, and the time integral are tabulated as functions of the impact parameter and the relative kinetic energy for each of three repulsive potentials. The classical theory of scattering was used as the basis for the calculations. The potentials used are the Born-Mayer (exponential), the Bohr (exponentially screened Coulomb), and the Thomas-Fermi. (auth)

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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The line width of one of the hynerfine components in solutions of Mn(ClO/ sub 4/)/sub 2/ containing added NaCl and Na/sub 2/SO/sub 4/ was studied from 20 to 200 deg C at 9000 Mc/sec. The chloride ion contributes littie broadening at 0.1 M below 80 deg C but considerable broadening is obtained above this temperature. The sulfate contributes broadening at all temperatures. The rates of formation of inner-sphere'' and outersphere'' complexes are discussed together with their rates of relaxation. At the lower temperatures the outersphere'' complexes primarily contribute to the broadening while at the higher temperatures the inner-sphere'' complexes also contribute. From the broadening above 80%DEC the rates of formation of the inner-sphere'' complexes are evaluated. (auth)

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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 .