Zirconium base alloy used for light-water reactors and preparation method thereof

Abstract

The invention discloses a zirconium base alloy used for light-water reactors. The zirconium base alloy contains, by weight, 0.30-0.69% of tin, 0.20-0.50% of niobium, 0.20-0.40% of iron, 0.01-0.09% of copper, 0.07-0.20% of oxygen, 0.005-0.03% of silicon and the balance zirconium. According to the invention, the minimum total percentage of the added copper, the silicon and the oxygen is limited to 0.13%, and the matching performance among the copper, the silicon and the oxygen is considered, so that the corrosion resistance of the zirconium base alloy is improved; meanwhile, the mechanical property, the radiation growth resistance and the radiation creeping resistance of the alloy can be improved.

Description

technical field [0001] The invention relates to the field of zirconium alloy materials, in particular to a zirconium-based alloy used in light water reactors and a preparation method thereof. Background technique [0002] Zirconium-based alloys are widely used as cladding materials and core structure materials for water-cooled power reactors due to their small thermal neutron absorption cross-section, good corrosion resistance and good mechanical strength in high-temperature water and high-temperature steam. With the development of nuclear power reactor technology in the direction of increasing fuel burnup, reducing fuel cycle costs, increasing reactor thermal efficiency, and improving safety and reliability, the corrosion resistance and creep resistance of zirconium-based alloys for key core component fuel element cladding materials Performance, hydrogen absorption performance, mechanical properties and radiation dimensional stability put forward higher requirements. [00...

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Problems solved by technology

[0015] However, the cooling rate of the core of the large-sized ingot is insufficient after the β-phase quenching process, and precipitates are inevitably generated at the α-phase boundary. The precipitates in the existing zirconium alloy processing technology are distributed in bands, and in the The α-phase hot rolling / hot extrusion process grows unevenly during the heat preservation process, so that the second phase particles in the zirconium alloy cannot be dispersed, resulting in poor plastic deformation ability of zirconium alloy and poor plastic processing ability of zirconium alloy

In addition, the precipitated phase is distributed in a band shape and grows unevenly during the heat preservation process of the α-phase hot rolling / hot extrusion process, resulting in a larger particle size of the second phase in the zirconium alloy and unable to disperse the distribution, resulting in the formation of zirconium alloys. Decreased corrosion resistance of core structural materials in nuclear reactors

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