ZIRCONIUM ALLOYS FOR NUCLEAR FUEL CLADDINGS, HAVING A SUPERIOR OXIDATION RESISTANCE IN THE HIGH TEMPERATURE PRESSURIZED WATER AND STEAM, AND THE PREPARATION METHOD OF ZIRCONIUM ALLOYS NUCLEAR FUEL CLADDINGS USING THEREOF

摘要

PURPOSE: A zirconium alloying composition for a nuclear fuel cladding pipe and a method of manufacturing a nuclear fuel cladding pipe of zirconium alloys using thereof are provided to obtain an excellent corrosion resistance of a nuclear fuel cladding pipe not only in a normal operation condition of a nuclear reactor but also in a hot-pressing water and a steam corrosion environment. CONSTITUTION: A zirconium alloying composition for a nuclear fuel cladding pipe comprises1.0-1.6 weight% of niobium (Nb), more than one kind of element selected from a group consisting of iron (Fe), chrome (Cr), and copper (Cu), 0.1-0.15 weight% of oxygen (O), 0.008-0.012 weight% of silicon (Si), and remainders of zirconium (Zr). If iron (Fe) is selected, 0.1-0.6 weight% of iron (Fe) is included. If chrome (Cr) is selected, 0.1-0.15 weight% of chrome (Cr) is included. If copper (Cu) is selected, 0.05-0.3 weight% of copper (Cu) is included. 0.15-0.3 weight% of tin (Sn) is included. [Reference numerals] (AA) Amount of weight increase (mg/dm^2); (BB) 400 °C steam 750 days; (CC) Example; (DD) Comparative example