FeCrAl base alloy material for nuclear fuel cladding material

Abstract

The invention relates to a FeCrAl base alloy material for a nuclear fuel cladding material. With the total weight of the FeCrAl base alloy material as a standard, the alloy material comprises 6%-16% of Cr, 3%-8% of Al, 0.001%-1% of Y, 0.1%-4% of Mo, 0.01%-0.5% of Si, 0.001%-0.5% of C, less than or equal to 500 ppm of N, less than or equal to 1000 ppm of O, less than or equal to 500 ppm of P, less than or equal to 500 ppm of S and the balance Fe. A FeCrAl base alloy shows the excellent antioxygenic property in the 1200 DEG C vapor environment, the excellent accident fault-tolerant ability is achieved and is obviously superior to that of a Zr base alloy, the machining performance is good, and the FeCrAl base alloy material can be used as core structural materials such as fuel element cladding, fuel element composite cladding, fuel cladding coatings and positioning grillage stripes in nuclear power station pressurized water reactors.

Description

technical field [0001] The invention belongs to the technical field of fuel cladding, and in particular relates to an FeCrAl-based alloy material for a nuclear fuel cladding material which is fault-tolerant to nuclear pressurized water reactor accidents. Background technique [0002] The cladding material of nuclear fuel elements is the first safety barrier of nuclear power plants and an important part to ensure that nuclear power plants can prevent nuclear leakage under normal operation and accident conditions. The Fukushima nuclear accident in Japan in 2011 revealed that the existing light water reactor nuclear fuel cladding zirconium alloys have major safety risks in resisting severe accidents. After the Fukushima nuclear accident, in order to further improve the accident tolerance of nuclear fuel cladding, the world's nuclear power developed countries have successively started to develop new nuclear fuel cladding to improve the safety of nuclear power plants. [0003] O...

AI Technical Summary

Problems solved by technology

The 2011 Fukushima nuclear accident in Japan revealed that the existing light water reactor nuclear fuel cladding zirconium alloys have major safety risks in resisting severe accidents

However, the existing nuclear fuel cladding materials, such as commercial zirconium alloy M5 for nuclear power plants, have poor water vapor oxidation resistance at 1200 °C.

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