The invention relates to a zirconium alloy which is resistant to corrosion in drop shadows for a fuel assembly component for a boiling water nuclear reactor. Said alloy is characterised in that it is composed of, in weight percentages: ' Nb = 0,4 - 4,5% ' Sn = 0,20 - 1,7% ' Fe = 0,05 - 0,45% ' Fe + Cr + Ni + V = 0,05 - 0,45% avec Nb 9 x [0,5-(Fe+Cr+Ni+V)] ' S = traces - 400ppm ' C = traces - 200ppm ' Si = traces - 120ppm ' O = 600 - 1800ppm, the remainder being Zr and impurities resulting from the production method. The alloy according to the invention is also characterised in that, during the production, after its last hot deformation, it was subjected to at least one thermal treatment between 450 and 610°C for a total duration of at least 4 hours, and at least one cold-rolling process at a rolling rate of at least 25 %; and in that a final thermal treatment is carried out between 450°C and 610°C for between 1 minute and 20 hours. The invention also relates to a fuel assembly component produced using said alloy, a fuel assembly comprising said alloy, and the use of same.