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FeCrAl alloy material for nuclear reactor fuel cladding material

A nuclear reactor fuel and alloy material technology, which is applied in the direction of reactor fuel elements, reactors, fuel element assembly, etc., can solve the problems of poor water vapor oxidation resistance, achieve excellent oxidation resistance, improve water vapor oxidation resistance, and comprehensive The effect of excellent performance

Inactive Publication Date: 2017-02-08
SUZHOU NUCLEAR POWER RES INST +3
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  • Abstract
  • Description
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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.

Method used

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  • FeCrAl alloy material for nuclear reactor fuel cladding material

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Embodiment Construction

[0016] The present invention will be further described below through specific examples.

[0017] Fe, Cr, Al, Y, Mo, Nb, and Si elements were mixed according to weight percentage and prepared into 5 alloy ingots by vacuum induction melting method. The chemical composition analysis of 5 ingots was sampled. The composition is shown in Table 1. The 5 ingots were forged, hot-rolled, extruded and annealed to produce FeCrAl alloy pipes with corresponding compositions.

[0018] The five FeCrAl-based alloys of the present invention and the commercial zirconium alloy M5 for nuclear power plants were subjected to a high-temperature steam oxidation test in a high-temperature steam oxidation equipment. The oxidation temperature was 1200 °C and the oxidation time was 1 h. See Table 1 for the results. Table 1 shows the proportions of FeCrAl-based components of five FeCrAl-based alloys according to the present invention, ie, Examples 1-5, and their oxidation weight gain under the above-mentio...

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Abstract

The invention relates to a FeCrAl alloy material for a nuclear reactor fuel cladding material. Based on the total weight of the FeCrAl alloy material, the FeCrAl alloy material is prepared from the following components: 6-24% of Cr, 3-12% of Al, 0.001-0.8% of Y, 0.1-4% of Mo, 0.01-5% of Nb, 0.05-1% of Si, less than or equal to 300ppm of C, less than or equal to 300ppm of N, less than or equal to 1000ppm of O, less than or equal to 100ppm of P, less than or equal to 100ppm of S and the balance of Fe. The FeCrAl alloy material disclosed by the invention shows excellent oxidation resistance in a 1200-DEG C water vapor environment simulating an LOCA working condition, has favorable accident fault-tolerant capability, is obviously better than a Zr-based alloy, is favorable in processability and can be used for preparing reactor core structural materials such as a fuel element cladding, a fuel element composite cladding, a fuel cladding coating and a locating grillwork strip.

Description

technical field [0001] The invention belongs to the technical field of fuel cladding, and in particular relates to a FeCrAl alloy material for a nuclear reactor fuel cladding material which is fault-tolerant to nuclear pressurized water reactor accidents. Background technique [0002] The nuclear fuel cladding tube is the first safety barrier of the nuclear power plant, which protects the fuel pellets from the erosion of the coolant, prevents the leakage of fission products into the primary circuit, and maintains the geometry of the fuel elements. Fuel cladding needs to withstand high temperature, high pressure and strong neutron radiation in the reactor, and is subject to fission gas pressure, corrosion, fuel swelling, hydrogen absorption and embrittlement, and is threatened by coolant pressure, erosion, vibration and corrosion, and hydrogen embrittlement. Therefore, the performance of the nuclear fuel cladding tube is very important, which is related to the safety of the n...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C38/22C22C38/06C22C38/02G21C3/07G21C3/34
CPCC22C38/001C22C38/002C22C38/005C22C38/02C22C38/06C22C38/22G21C3/07G21C3/3424Y02E30/30
Inventor 柏广海孙文儒张晏玮余伟炜张伟红王荣山刘二伟郭立江杜晨曦梅金娜蔡尧
Owner SUZHOU NUCLEAR POWER RES INST
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