this report documents the fabrication and characterization for 3 westinghouse-design fuel rods supplied to the high burnup effects program, task 3. fuel rods being supplied to the high burnup effects program 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 (times) 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. the rods are essentially the westinghouse 17 (times) 17 design; the exceptions are as given. other design information relative to the rods supplied is listed in table 1-1. specific rod identities and the estimated eol heat flux and burnup are listed in table 1-2. the clad material is westinghouse 17 (times) 17 design, cold-worked and stress-relief annealed zircaloy-4 tubing fabricated by the specialty metals division (smd) of westinghouse electric corporation. 30 figs., 24 tabs