FeCrAl alloy material for preparing Nuclear reactor fuel cladding material

Abstract

The invention relates to a FeCrAl alloy material for preparing a Nuclear reactor fuel cladding material. By taking the total weight of the FeCrAl alloy material as a benchmark, the FeCrAl alloy material is composed of the following components: 5%-25% of Cr, 3%-15% of Al, 0.01%-3.3% of Si, 0.001%-1% of Y, 5% or less of Mo, 5% or less of Nb, 1000 ppm or less of C, 1000 ppm or less of N and the balance of Fe and inevitable trace elements. The nuclear fuel cladding FeCrAl alloy has excellent oxidation resistance at the 1200 DGE C water vapor environment, which is obviously better than commercial M5 zirconium alloys, and the requirement for accident fault tolerance of the nuclear power plant is met. The alloy can be used for the preparation of oxide dispersion strengthened iron-base alloy base materials for fuel element cladding pipes, composite cladding pipes, zirconium alloy coatings and nuclear fuel cladding pipes, and core structural materials of positioning grid stripes and the like.

Description

technical field [0001] The invention belongs to the technical field of fuel cladding, and in particular relates to an FeCrAl alloy material for nuclear reactor fuel cladding materials which are anti-accident. Background technique [0002] The "Design Guidelines for Emergency Core Cooling System of Pressurized Water Reactor Nuclear Power Plant" stipulates that the emergency core cooling system should meet the requirements of the maximum temperature, reaction equivalent and hydrogen release capacity of nuclear fuel cladding, which cannot meet the safety requirements of nuclear power plants. . After the Fukushima nuclear accident in Japan in 2011, all countries are exploring a new generation of accident-resistant fuel cladding to further improve the safety of nuclear reactors under accident conditions, and to deal with and restore emergency cooling systems for nuclear power plants under emergency conditions Gain valuable time. [0003] The basis for the selection of anti-acci...

AI Technical Summary

Problems solved by technology

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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