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 is composed of the following components: Nb0.2%-0.4%, Sn0.4%-0.6%, Fe0. 3%~0.5%, Cr0.2%~0.3%, V0.1%~0.3%, O600~1200ppm, C≤100ppm, N≤80ppm and the balance of Zr, among them, the weight ratio of Nb to Fe≤1, Fe The weight ratio to Cr is 1.4-1.6:1. The invention optimizes the design of the existing zirconium alloy formula, so that when the Sn content is small, it still has excellent corrosion resistance and good mechanical properties.

Description

technical field [0001] The invention relates to the field of zirconium alloy materials, in particular to a corrosion-resistant zirconium alloy which can be used as a fuel rod cladding material in a nuclear reactor core of a light water nuclear power plant. 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...

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Problems solved by technology

Although the alloy has the above advantages, the tin content is still high

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