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FeCrAl base alloy for nuclear reactor core and preparing method of alloy

A nuclear reactor and base alloy technology, applied in the field of iron-based alloy structural materials and special alloy materials, can solve the problems of high temperature oxidation resistance, toughness and high temperature resistance strength that cannot effectively meet the performance requirements of nuclear reactor cores, and achieve excellent high temperature oxidation Performance, prevention of hardening and embrittlement tendency, effect of grain refinement

Active Publication Date: 2017-09-08
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

[0006] The technical problem to be solved by the present invention is: the high-temperature oxidation resistance, toughness and high-temperature resistance strength of the FeCrAl-based alloy materials in the prior art cannot effectively meet the performance requirements of the nuclear reactor core, and the purpose is to provide a nuclear reactor core Using FeCrAl-based alloy and its preparation method to ensure high toughness and high temperature resistance strength while effectively ensuring significant high temperature oxidation resistance

Method used

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  • FeCrAl base alloy for nuclear reactor core and preparing method of alloy

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Embodiment 1

[0034] A FeCrAl-based alloy for a nuclear reactor core, the specific composition of which is shown in Table 1. In Table 1, 1 to 5 are specific proportions of the present invention, and 1# to 3# are specific proportions of alloys for comparison.

[0035] Among them, 1# is a comparative example without adding metal elements such as Ta and Hf on the basis of 3, 2# is a comparative example of increasing Cr and Al content on the basis of 3, and 3# is a comparative example of reducing Cr and Al on the basis of 3 content comparison.

[0036] Table 1

[0037]

[0038] Adopt the composition in above-mentioned table 1, adopt following method to prepare alloy, concrete preparation method is:

[0039] (1) prepare 20-30 kilograms of ingots with industrial pure iron and high-purity alloys with a purity greater than 99.9% according to the formula in Table 1;

[0040] (2) The above ingot is subjected to a high temperature homogenization annealing temperature. Annealing temperature: not...

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Abstract

The invention discloses a FeCrAl base alloy for a nuclear reactor core and a preparing method of the alloy. The problem that high-temperature oxidation resistance performance, toughness and high-temperature resistance strength of a FeCrAl base alloy material in the prior art cannot effectively meet the performance requirement of the nuclear reactor core is solved. The alloy comprises 12.5 to 14.5 wt% of Cr, 3.5 to 5.5 wt% of Al, 1.5 to 3 wt% of Mo, 1 to 3 wt% of Nb, 0.1 to 0.3 wt% of Si, 0.1 to 0.2 wt% of Ta, 0.1 to 0.2 wt% of Hf, 0 to 0.2 wt% of Ga, 0.1 to 0.2 wt% of Ni, 0.05 to 0.1 wt% of Ce, not larger than 0.008 wt% of C, not larger than 0.005 wt% of N, not larger than 0.003 wt% of O, and the balance Fe and inevitable impurities. The alloy has the excellent high-temperature oxidation resistance performance, heat stability, mechanical property and the like.

Description

technical field [0001] The invention relates to the technical field of iron-based alloy structural materials and special alloy materials, in particular to a FeCrAl-based alloy for nuclear reactor cores, and discloses a preparation method of the FeCrAl-based alloy. Background technique [0002] After the Fukushima nuclear accident in Japan, it is required that the fuel element cladding materials for the next generation and future advanced nuclear power water reactors must have better resistance to high-temperature water vapor oxidation, high-temperature strength and High temperature stability, which can provide a greater safety margin and avoid potential core melting accidents, also known as accident-resistant cladding materials. The research shows that the FeCrAl alloy containing appropriate amounts of Cr, Al, and Si has good radiation resistance and high temperature oxidation resistance, making it a very potential cladding material in the research and development of acciden...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C38/06C22C38/02C22C38/44C22C38/48C21D8/00
CPCC21D8/005C22C38/002C22C38/004C22C38/005C22C38/02C22C38/06C22C38/44C22C38/48
Inventor 张瑞谦王辉潘钱付张忠伦刘超红陈勇王晓敏
Owner NUCLEAR POWER INSTITUTE OF CHINA
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