FeCrAl alloy material for preparing Nuclear reactor fuel cladding material

A technology for nuclear reactor fuel and alloy materials, which is applied to the assembly of reactor fuel elements, reactors, and fuel elements, can solve problems such as poor resistance to water vapor oxidation, meet the requirements of accident fault tolerance, prolong emergency response time, and improve resistance to water vapor. Effect of Water Vapor Oxidation Properties

Inactive Publication Date: 2017-02-15
SUZHOU NUCLEAR POWER RES INST +3
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Problems solved by technology

However, the existing nuclear fuel cladding materials, such as commercial zirconium al

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  • FeCrAl alloy material for preparing Nuclear reactor fuel cladding material

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Embodiment Construction

[0014] The present invention will be further described below through specific examples.

[0015] Fe, Cr, Al, Si, Y, Mo, Nb, C, N (wherein, N is Cr 2 The elements added in the form of N) were mixed by weight percentage and prepared into 6 alloy ingots by vacuum induction melting method. The chemical composition analysis of the 6 ingots was sampled. The composition is shown in Table 1. Samples were cut from 6 ingots for high temperature water vapor oxidation test.

[0016] For the six samples of the present invention, that is, Examples 1-6 and the commercial zirconium alloy M5 for nuclear power plants, a high-temperature steam oxidation test was carried out in a high-temperature steam oxidation equipment. Table 1 shows the distribution ratio of FeCrAl-based components of Examples 1-6 according to the present invention and their oxidation weight gain under the respective above-mentioned water vapor oxidation conditions. The water vapor oxidation weight gain data of commercial z...

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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...

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Application Information

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IPC IPC(8): C22C38/06C22C38/02C22C38/22C22C38/26G21C3/07G21C3/34
CPCC22C38/005C22C38/02C22C38/06C22C38/22C22C38/26G21C3/07G21C3/3424Y02E30/30
Inventor 柏广海孙文儒张晏玮余伟炜张伟红王荣山刘二伟梅金娜杜晨曦耿建桥蔡尧
Owner SUZHOU NUCLEAR POWER RES INST
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