| 摘要 |
PURPOSE:To prevent the nodular corrosion of a Zr alloy as a material for a nuclear reactor by treating the alloy in a steam atmosphere contg. oxygen in an autoclave. CONSTITUTION:A Zr alloy such as zircaloy is treated in a steam atmosphere under about 10<3>-10<6>Pa partial pressure of oxygen in an autoclave. The treatment is carried out at 400-500 deg.C under high pressure for 12-24hr. By the treatment, superior nodular corrosion resistance is provided to the Zr alloy. This method is applicable to a structural material for a fuel chanel for a boiling water type light water reactor, a fuel cladding pipe, etc. |
