Corrosion-resistant zirconium-tin-niobium alloy for nuclear reactor core and preparation method thereof

Abstract

The invention discloses a corrosion-resistant zirconium-tin-niobium alloy for nuclear reactor core, which is composed of the following components in mass percentage: Sn 0.6%-1.5%, Nb 0.1%-0.5%, Fe 0.1%-0.6%, Cr 0.1% ~0.5%, Cu 0.01%~0.3%, Mg 0.005%~0.2%, O 600ppm~1400ppm, the balance is Zr and unavoidable impurities. In addition, the present invention also discloses a method for preparing the zirconium-tin-niobium alloy, the method is: 1. preparing a Zr-Cu-Mg master alloy; 2. preparing a Zr-Nb master alloy; 3. preparing a Zr-Sn-Fe-Cr Master alloy; 4. Preparation of zirconium-tin-niobium alloy. The zirconium-tin-niobium alloy of the invention has excellent corrosion resistance and mechanical properties, and is suitable for cladding materials, grids and other structural components of nuclear reactor fuel rods in nuclear power plants.

Description

technical field [0001] The invention belongs to the technical field of zirconium alloy materials, in particular to a corrosion-resistant zirconium-tin-niobium alloy for nuclear reactor cores and a preparation method thereof. Background technique [0002] In the nuclear power industry, zirconium and its alloys have the outstanding advantage of small thermal neutron absorption cross section, which can ensure that there are enough thermal neutrons in the atomic energy reactor to maintain the normal operation of the reactor. In addition, zirconium alloys also have the advantages of good machinability, high corrosion resistance, and moderate mechanical strength, so they are widely used as structural materials for reactors, such as cladding materials, spacer grids, and end plugs. [0003] With the further development of the nuclear power industry, in order to increase the competitiveness of nuclear power, it is necessary to increase the fuel consumption of the reactor to reduce th...

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Problems solved by technology

[0003] With the further development of the nuclear power industry, in order to increase the competitiveness of nuclear power, it is necessary to increase the fuel consumption of the reactor to reduce the cost of nuclear power. When the fuel consumption is lower than 30GWd / tU, the conventional Zr-4 alloy cladding can meet the requirements , when the fuel consumption is 40-50GWd / tU, it is necessary to improve the Zr-4 alloy cladding to meet the use requirements of the components, but when the fuel consumption reaches 60GWd / tU, the improved Zr-4 alloy cannot meet the requirements, and a new Zirconium alloys are used to make the cladding. For reactors, the main limiting factors to further increase the fuel consumption are the water-side corrosion and hydrogen absorption of the zirconium alloys of the fuel cladding. At the same time, as a structural part, it must have certain mechanical properties.

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