Zirconium alloy for nuclear reactor

Abstract

The invention discloses a zirconium alloy for a nuclear reactor. Based on the total weight of the zirconium alloy, the zirconium alloy comprises the following components: 0.1 to 0.2 percent of Nb, 0.7 to 0.8 percent of Sn, 0.3 to 0.4 percent of Fe, 0.05 to 0.25 percent of Cu, 0.01 to 0.1 percent of V, 0.05 or 0.15 percent of Cr, 0.06 to 0.14 percent of O, less than or equal to 100 ppm of C, less than or equal to 80 ppm of N and the balance of Zr. The zirconium alloy disclosed by the invention has high corrosion resistance in high-temperature steam at 400 and high-temperature steam at 427 DEG C and has high yield strength and breaking strength at room temperature; therefore, the safety and efficiency of a nuclear fuel assembly are improved, and the zirconium alloy meets the requirements ofcan materials of a nuclear reactor.

Description

technical field [0001] The invention relates to the field of zirconium alloy materials, in particular to a zirconium alloy material for nuclear reactors. Background technique [0002] The thermal neutron absorption cross section of zirconium is very small, and has good high temperature water corrosion resistance and mechanical properties, so zirconium alloys are widely used as cladding materials for fuel rods and structural elements of nuclear reactor cores in water-cooled nuclear reactors. With the development of nuclear power reactor technology in the direction of increasing fuel consumption, reducing fuel cycle costs, increasing reactor thermal efficiency, and improving safety and reliability, the corrosion resistance, hydrogen absorption performance, and Higher requirements are put forward for mechanical properties and radiation dimensional stability. Creep and fatigue will occur in fuel elements under service conditions (irradiation, high temperature, high pressure and...

AI Technical Summary

Problems solved by technology

At present, the most mature and widely used zirconium alloys are called Zr-2 and Zr-4 alloys. However, with the development of nuclear fuel assemblies in the direction of long life and high burnup, zirconium alloys as reactor structural materials must be It has better comprehensive properties such as corrosion resistance, creep resistance, and radiation growth resistance. At this point, Zr-2 and Zr-4 alloys can no longer meet the requirements

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