The thin oxide layer growing on the zirconium alloy is dense and adherent and therefore is protective against further oxidation and hydrogen ingress, which is deleterious to zirconium pressure tube used in nuclear power stations because it facilitates formation of zirconium hydrides. Heat treatment and other surface modification methods were applied to zirconium alloys and the texture was investigated. Thermogravimetric analytic (TGA) was used for oxidation kinetics studies. The oxidation kinetics data show the variation of the oxidation rate due to the difference of texture and microstructure and the oxidation resistance is improved after the substrate is cold worked and heat treated. After cold work and heat treatment, the texture of substrate changes from (11-20)[1-100] to (11-23)[1-100].