ZIRCONIUM ALLOYS FOR NUCLEAR FUEL CLADDINGS HAVING A SUPERIOR OXIDATION RESISTANCE IN THE REACTOR ACCIDENT CONDITIONS, ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS PREPARED BY USING THEREOF AND METHOD OF PREPARING THE SAME

摘要

PURPOSE: Zirconium alloys for nuclear fuel claddings and zirconium alloy nuclear fuel claddings manufactured by using thereof and a method of manufacturing thereof are provided to secure an excellent oxidation resistance of a nuclear fuel cladding not only under an accident condition but also in a normal operation condition of a nuclear reactor. CONSTITUTION: Zirconium alloys for nuclear fuel claddings comprise 1.0-1.2 weight% of niobium (Nb), elements which is more than one kind selected from a group consisting of tin (Sn), iron (Fe), and chrome (Cr), 0.02-0.1 weight% of copper (Cu), 0.1-0.15 weight% of oxygen (O), 0.008-0.012 weight% of silicon (Si), and remainders of zirconium (Zr). A composition selected among 0.1-0.3 weight% of tin (Sn), and 0.3-0.8 weight% of iron (Fe), and 0.1-0.3 weight% of chrome (Cr) is included. The Zirconium alloys comprise 1.1 weight% of niobium (Nb), two kinds of elements selected from a group consisting of tin (Sn), iron (Fe), and chrome (Cr), 0.05 weight% of copper (Cu), 0.12 weight% of oxygen (O), 0.01 weight% of silicon (Si), and remainders of zirconium (Zr). A composition selected among 0.2 weight% of tin (Sn), and 0.5 weight% of iron (Fe), and 0.1-0.2 weight% of chrome (Cr) is included. [Reference numerals] (AA) Amount of weight increase (mg/dm^2); (BB) 1200 C 1800 seconds; (CC) Example 1; (DD) Example 4; (EE) Example 6; (FF) Comparative example 2