Development and Properties of Coextruded Zircaloy-Clad Uranium Fuel Elements With Integral End Seals Terminal Report to Hanford Atomic Products Operation General Electric Co.

摘要

Prototype uranium fuel elements clad with Zircaloy and with integral end seals of Zircaloy were fabricated by the coextrusion process. Research and development efforts to produce successful end closures, uniform cladding, and metallurgical bonds are described. Details are given of the breakdown of large diameter stock by primary extrusion for use as billet components, and the fabrication of long lengths of clad rod of 0.630-inch and 1.000-inch diameter is described.