Zirconium alloy material for light water reactor under higher burnup

Abstract

The invention discloses a zirconium alloy material for a light water reactor under higher burnup. The zirconium alloy material comprises 0.10-0.40 weight% of tin, 0.50-1.50 weight% of niobium, 0.01-0.20 weight% of iron and 0.06-0.20 weight% of oxygen, and further comprises 0.01-0.09 weight% of vanadium and / or 0.01-0.09 weight% of copper and the balance of zirconium. The zirconium alloy has excellent corrosion resistance; and compared with the zirconium alloy in the prior art, the zirconium alloy has more excellent corrosion resistance in high-temperature pure water, and is suitable for fuel rod cladding materials and corrosion resistant zirconium alloy materials of grillwork strips and structural parts under higher burnout of nuclear reactors.

Description

technical field [0001] The invention relates to an alloy material, in particular to a zirconium alloy material used in a light water reactor with relatively high burnup. Background technique [0002] The earliest zirconium alloy used in pressurized water reactors is Zr-4 alloy. The average unloading fuel consumption of foreign pressurized water reactor fuel assemblies was 30-35GWd / tU in the late 1970s. The Sn content of the Zr-4 alloy is relatively high, ranging from 1.2 to 1.7%. Operation experience shows that high Sn content of the alloy is not good for corrosion resistance. Therefore, Westinghouse Corporation of the United States began to conduct research on ZIRLO alloys in the 1970s, and its Sn content was only 0.90-1.10%. As a Zr-Sn-Nb alloy, its Nb content is 0.80-1.20%, Fe content is 0.08-0.12%, and O content is 0.105-0.145%. When the internal combustion consumption of the PWR is 60GWd / tU, the corrosion resistance of the ZIRLO alloy is much better than that of the...

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Problems solved by technology

[0012] 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 uneven growth of the α-phase hot rolling process during the heat preservation process leads to the inability to disperse the second phase particles in the zirconium alloy, resulting in poor plastic deformation ability of the zirconium alloy and poor plastic processing ability of the 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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