Stainless steel alloy, preparation method thereof and stainless steel cladding of fuel assembly

A technology of fuel assembly and stainless steel, which is applied in the field of reactor nuclear fuel assembly, can solve the problems of affecting stainless steel welding performance and thermal processing performance, reducing corrosion resistance, steel brittle corrosion resistance, etc., to improve machining performance and corrosion resistance Performance, effect of reducing Cr content

Inactive Publication Date: 2016-12-14
CHINA NUCLEAR POWER TECH RES INST CO LTD +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0009] (2) σ phase brittleness
For medium and high Cr ferritic stainless steel, heating in the range of 600 ~ 980 ° C is easy to form σ phase, resulting in embrittlement and reducing its corrosion resistance
[0010] (3) high temperature brittleness
When high-Cr ferritic stainless steel is heated above 950°C, the steel often becomes brittle and accompanied by poor corrosion resistance during the cooling process, which affects the welding performance and hot working performance of stainless steel.

Method used

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  • Stainless steel alloy, preparation method thereof and stainless steel cladding of fuel assembly
  • Stainless steel alloy, preparation method thereof and stainless steel cladding of fuel assembly
  • Stainless steel alloy, preparation method thereof and stainless steel cladding of fuel assembly

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preparation example Construction

[0045] The preparation method of the first embodiment of the stainless steel alloy of the present invention may comprise the following steps:

[0046] S1. Melting the raw materials of each component according to the mass percentage of each component to obtain a smelting liquid.

[0047] Among them, smelting can be realized by any one of vacuum induction furnace, non-vacuum induction furnace, resistance furnace, electric arc furnace + refining outside the furnace. The raw materials for each component are commercially available.

[0048] S2. Casting to produce a stainless steel alloy. The casting temperature is 1550°C to 1650°C.

[0049]In the first embodiment, each component is added in the form of a single substance, followed by smelting and casting in sequence to obtain a stainless steel alloy.

[0050] The preparation method of the second embodiment of the stainless steel alloy of the present invention may comprise the following steps:

[0051] S1. Prepare an Al-Y master...

Embodiment 1

[0062] The vacuum smelting process is used to pre-prepare Al-Y master alloy, wherein the weight percentage of yttrium is 20%, and the FeCrAl ferritic stainless steel alloy is obtained through metering, batching, smelting and casting by adopting the master alloy secondary feeding method. Among them, the mass percentage (wt%) of each component is as follows: Cr 10%, Al 6%, Nb 0.6%, Mo 3%, Ti 0.3%, Si0.5%, Zr 0.5%, W 0.5%, Y 0.3%, The balance is Fe.

[0063] The yield strength of the prepared stainless steel alloy is greater than 450MPa, the tensile strength is greater than 500MPa, and the elongation at break is greater than 25% at room temperature; at 300°C, the yield strength is greater than 250MPa, and the tensile strength is greater than 400MPa. Alloy ingots are uniformly annealed at 1200°C, forged at 800-1200°C to form bars, then perforated, hot-rolled at 800-1050°C for multiple passes, cold-rolled, intermediate annealed, and finally stress-relieved annealed at 700°C. Corre...

Embodiment 2

[0065] The vacuum smelting process is used to pre-prepare Al-Y master alloy, wherein the weight percentage of yttrium is 20%, and the FeCrAl ferritic stainless steel alloy is obtained through metering, batching, smelting and casting by adopting the master alloy secondary feeding method.

[0066] Among them, the mass percentage (wt%) of each component is as follows: Cr 13%, Al 5%, Nb 0.4%, Mo 1%, Ti0.2%, Si 0.5%, Zr 0.5%, W 0.5%, Y 0.3%, The balance is Fe.

[0067] The yield strength of the prepared stainless steel alloy is greater than 450MPa, the tensile strength is greater than 500MPa, and the elongation at break is greater than 25% at room temperature; at 300°C, the yield strength is greater than 250MPa, and the tensile strength is greater than 400MPa. Alloy ingots are uniformly annealed at 1200°C, forged at 800-1200°C to form bars, then perforated, hot-rolled at 800-1050°C for multiple passes, cold-rolled, intermediate annealed, and finally stress-relieved annealed at 700°...

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Abstract

The invention discloses stainless steel alloy, a preparation method of the stainless steel alloy and a stainless steel cladding of a fuel assembly. The stainless steel alloy comprises, by mass, 8%-18% of chromium, 4%-8% of aluminum, 0.1%-1% of niobium, 0.1%-4% of molybdenum, 0.1%-2% of titanium, 0.01%-2% of silicon, 0.1%-2% of zirconium, 0.05%-2% of tungsten, 0.005%-1% of yttrium and the balance Fe. According to the stainless steel alloy, under the synergistic effect of the microelements like Cr, Nb and Mo, the Cr content is lowered, the brittle phase is restrained, the machining property of the stainless steel alloy is improved, and the corrosion resistance, high-temperature mechanical property and ductility of the stainless steel alloy are also improved. By limiting the carbon and nitrogen contents of impurities in the stainless steel alloy, the effective Cr content in a solid solution is increased; and moreover, formed carbide and nitride are beneficial to grain refinement, and the strength and plasticity of manufactured tubes are improved.

Description

technical field [0001] The invention relates to the technical field of reactor nuclear fuel assemblies, in particular to a stainless steel alloy suitable for fuel assemblies, a preparation method thereof, and a stainless steel cladding of fuel assemblies. Background technique [0002] The reactor nuclear fuel assembly is a key component of the reactor core, including guide tubes, cladding of fuel rods, upper end plugs, lower end plugs, inner and outer strips of the assembly grid, etc. The main function is to protect the fuel pellets from coolant erosion , Release energy and shield strong radioactive substances from leaking. During operation, nuclear fuel assemblies need to withstand threats such as high internal and external pressure, high temperature, fuel swelling, and embrittlement caused by hydrogen absorption. According to. Therefore, nuclear fuel assemblies need to meet various performance requirements such as metallurgy, heat transfer, and machinery, such as: [00...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C38/28C22C38/26C22C38/22C22C38/06C22C38/02C22C33/04
CPCC22C38/28C22C33/04C22C38/005C22C38/02C22C38/06C22C38/22C22C38/26
Inventor 黄华伟李锐刘彤任啟森孙茂州高思宇薛佳祥武海龙黄恒李思功孟繁良卢志威严岩
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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