Zirconium-base alloy used for light-water reactor

Abstract

The invention relates to a zirconium alloy material, particularly to a zirconium-base alloy used for a light water reactor. The zirconium-base alloy is composed of (wt %) Sn 0.80-1.20, Nb 0.90-1.25, Fe 0.12-0.45, O 0.06-0.15, C less than 0.15, N less than 0.008, and zirconium and impurities in balance. By adding Fe and O two elements based on the current Zr-Sn-Nb alloy, the zirconium-base alloy with good corrosion-resisting property in all corrosion tests using 360 DEG C deionized water, 360 DEG C lithium-containing water solution, 400 DEG C steam and 500 DEG C can be prepared. The inventive zirconium-base alloy can be used as structural material of a nuclear reactor core.

Description

Technical field [0001] The invention relates to a zirconium alloy material, in particular to a zirconium-based alloy used in a light water reactor. Background technique [0002] In the development process of light water reactors, including boiling water reactors and pressurized water reactors, fuel design has put forward high requirements on the structural components of the reactor core, such as fuel element cladding, grids, and guide tubes. Currently, these parts are usually made of Zr-2 and Zr-4 alloys. The design of high fuel consumption requires extending the residence time of these components in the stack and increasing the temperature of the coolant, which makes the zirconium alloy components face a more severe corrosion and hydrogen absorption environment. These high requirements have promoted the research to improve the corrosion resistance of Zr-2 and Zr-4 alloys, and promoted the development of new zirconium alloys with better corrosion resistance and hydrogen absorptio...

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Problems solved by technology

Although people can accept the following point of view: the materials that pass the test in 360 °C aqueous solution and 400 °C steam can be used in pressurized water reactors, and those that pass the test in 360 °C lithium-containing aqueous solution are more suitable for use in pressurized water reactors with high lithium concentrations In working conditions, those that pass the test in steam above 500°C can be used in boiling water reactors; moreover, in the above-mentioned published documents, it is proved by test examples that the relevant zirconium alloys are better than the previous zirconium-2 and zirconium-4 alloys have better properties, but it is still unknown whether these alloys can be actually applied in practice and show satisfactory technical effects

Moreover, none of the above-mentioned literatures gives information about the furuncle corrosion resistance of alloys in 500°C steam.

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