ZIRCONIUM ALLOYS FOR NUCLEAR FUEL CLADDING, HAVING A SUPERIOR OXIDATION RESISTANCE IN A SEVERE REACTOR OPERATION CONDITIONS, AND THE PREPARATION METHOD OF ZIRCONIUM ALLOYS NUCLEAR FUEL CLADDINGS USING THEREOF

摘要

Disclosed are a zirconium alloy composition for a nuclear fuel cladding having a superior oxidation resistance under a severe reactor operation condition and a method of preparing zirconium alloy nuclear fuel claddings by using the same. The zirconium alloy composition includes 1.8 to 2.0 % by weight of niobium (Nb), at least one element selected from iron (Fe), chromium (Cr) and copper (Cu), 0.12 % by weight of oxygen (O), 0.01 % by weight of silicon (Si) and a remaining amount of zirconium (Zr). The zirconium alloy composition for the nuclear fuel cladding includes 0.1 to 0.2 % by weight of Fe, 0.1 % by weight of Cr, and 0.03 to 0.2 % by weight of Cu. According to the present invention, the nuclear fuel cladding is manufactured using the zirconium alloy composition for the nuclear fuel cladding, which represents superior oxidation resistance under a severe reactor operation condition, so that the superior oxidation resistance of the nuclear fuel cladding can be ensured under an accident condition as well as under a normal operation condition of a reactor. In addition, the nuclear fuel cladding satisfying power increase, load following operation, and the long cycle operation conditions can be manufactured so that the economical efficiency and stability of the nuclear fuel can be simultaneously improved.