Zirconium alloy material applied to nuclear reactor

Abstract

The invention discloses a zirconium alloy material applied to a nuclear reactor, comprising the following components in percentage based on total weight of a zirconium alloy: N b 0.4%-0.6%, Fe 0.3%-0.4%, Cr 0.2%-0.3%, Cu 0.05%-0.15%, at least one of V 0.01%-0.05% and Ni 0.1%-0.2%, O 0.06%-0.14%, C <=1000 ppm, N <=80 ppm, and the balance of Zr. Research shows that the zirconium alloy disclosed by the invention is excellent in comprehensive performance, particularly good in corrosion resistance in pure water at 360 DEG C and in stream at 400 DEG C; and therefore, the zirconium alloy can be used as a can material of the nuclear reactor.

Description

technical field [0001] The invention relates to the field of zirconium alloy materials, in particular to a zirconium alloy material for nuclear pressurized water reactors. 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 will occur in fuel elements under service conditions (irradiation, high temperature,...

AI Technical Summary

Problems solved by technology

At present, the most mature and widely used zirconium alloys are called Zr-2 and Zr-4 alloys. However, with the development of nuclear fuel assemblies in the direction of long life and high burnup, zirconium alloys as reactor structural materials must be It has better comprehensive properties such as corrosion resistance, creep resistance, and radiation growth resistance. At this point, Zr-2 and Zr-4 alloys can no longer meet the requirements

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