ZIRCONIUM ALLOYS COMPOSITIONS AND PREPARATION METHOD HAVING LOW-HYDROGEN PICK-UP RATE AND RESISTANCE AGAINST HYDROGEN EMBRITTLEMENT

摘要

The present invention relates to zirconium alloy compositions having excellent low-hydrogen absorption and hydrogen embrittlement resistance, and a manufacturing method thereof. More specifically, the present invention relates to the zirconium alloy compositions comprising: (1) 1.0-1.4 wt% of Nb, 0.1-0.3 wt% of Sc, 0.04-0.06 wt% of Al, 0.1-0.3 wt% of Sn, 0.04-0.06 wt% of Fe, and a remainder of Zr; (2) 1.0-1.4 wt% of Nb, 0.1-0.3 wt% of Sc, 0.04-0.06 wt% of Al, 0.04-0.08 wt% of Cu, and a remainder of Zr; (3) 1.2-1.4 wt% of Nb, 0.1-0.3 wt% of Sc, 0.04-0.06 wt% of Al, 0.1-0.3 wt% of Cr, and a remainder of Zr. According to the present invention, the zirconium alloy compositions are properly controlled for a type of added element, dosage and heat processing temperature, and the like, to improve a low-hydrogen absorption and hydrogen embrittlement resistance; thereby delivering excellent low-hydrogen absorption and hydrogen embrittlement resistance when compared with a conventional zircaloy-4 alloys. Hydrogen is generated in a reaction of zirconium and water in view of an operating environment characteristic of a nuclear power plant, and hydrogen penetrates zirconium alloys by which hydrogen embrittlement may occur. The zirconium alloys of the present invention have excellent low-hydrogen absorption and hydrogen embrittlement resistance; thus can be utilized as a nuclear source coating pipe, a spacer grid, and a structure and the like in a nuclear power plant.