A zirconium alloy that is resistant to shadow corrosion for a boiling water nuclear reactor fuel assembly component, the alloy being characterized in that: its composition in percentages by weight is as follows: Nb=0.4%-4.5% Sn=0.20%-1.7% Fe=0.05%-0.45% Fe+Cr+Ni+V=0.05%-0.45%, with Nb≦9×[0.5−(Fe+Cr+V+Ni)] S=traces-400 ppm C=traces-200 ppm Si=traces-120 ppm O=600 ppm-1800 ppm the balance being Zr and impurities from processing; in that, during fabrication, after its last hot deformation, it is subjected to one or more heat treatments lying in the range 450° C. to 610° C. for a total duration of at least 4 h, with at least one cold rolling operation with a rolling ratio of at least 25%; and in that a final heat treatment operation is performed at a temperature in the range 450° C. to 610° C. for 1 minute to 20 hours. A fuel assembly component made of the alloy, a fuel assembly including the component, and the use thereof.