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Mackowiak, Brady

Publications and source records attributed to Mackowiak, Brady.

Extrusion Development Report

This report describes a fuel extrusion process developed under a cooperative research and development agreement (CRADA) between TerraPower, LLC, and Idaho National Laboratory.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Co-Extrusion of Zr Lined U-Zr Alloy Characterization Report

A feasibility study was undertaken to assess the feasibility of co-extruding U-10Zr and U-6Zr with a zirconium barrier on the outside surface. A U-10Zr and U-6Zr billet was cast, machined, and sealed in a zirconium can. The can was extruded with an extrusion ratio of approximately 35.5. After extrusion the extruded rods were sectioned for easier handling, radiographed, and metallographically examined. Radiography showed the rods to be solid with the exception of one location in the U-6Zr rod. Metallography showed the expected deformed microstructure in the longitudinal direction, although this was much less noticeable in the U-6Zr structure. Also seen in both rods microstructure was a zirconium gradient; the zirconium concentration was higher near the zirconium liner as compared to the interior of the rod. Based on the successful extrusion co-extrusion of U-Zr alloys with a zirconium liner is feasible.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗