To provide a method for producing zirconium alloy-based reactor core structural material having sufficient corrosion resistance, particularly excellent in uniform corrosion resistance and hydrogen absorption resistance in higher burn-up degree and for longer use than before.

Sn: 0.8-1.6wt.%, Fe: 0.17-0.25wt.%, Cr: 0.15-0.25wt.%, Ni: 0.01-0.08wt.% and impurity Si of concentration of 120ppm or less are contained, the residual is composed of Zr, and after zirconium alloy adjusted so as to satisfy Fe+Cr+Ni≤0.52wt.% is melted and made a piece of casting, hardening treatment is performed. Thereafter, rolling and annealing treatment are performed so that the total thermal input amount Σ A1 for the material may be in the range of 1×10-19-1×10-17.