Fabrication and Characterization of Westinghouse-Design Fuel Rods for The Super-Ramp Project: The Studsvik Super-Ramp Project.

摘要

This report documents the fabrication and characterization for 10 Westinghouse-design fuel rods supplied to the Studsvik SUPER-RAMP Project. Fuel rods being supplied to the SUPER-RAMP Project were initially designed and characterized for a Westinghouse ramp program. The rods were specifically intended for preirradiation in the BR-3 reactor and subsequent ramp testing in a reactor test loop. The 17 x 17 fuel rod diameter Core 4A BR-3 fuel assembly configuration was designed for removal of all 28 fuel rods and reconstitution of the assembly for subsequent irradiation cycles. The fuel was also characterized during fabrication to provide a well-defined base point for subsequent evaluation of power ramp performance. The initial Westinghouse ramp program was begun in 1974; fuel rods were fabricated in 1975 and loaded into assemblies in 1976. Irradiations began in mid-July 1976. Other design information relative to the rods supplied is listed and specific rod identities and the expected EOL heat flux and burnup are provided. The clad material is Westinghouse 17 x 17 design, cold-worked and stress-relief annealed Zircaloy-4 fabricated by the Specialty Metals Division (SMD) of Westinghouse Electric Corporation. 21 figs., 20 tabs.