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High-temperature water vapor corrosion resistant coating for surface of zirconium alloy cladding tube of nuclear power plant and preparation method of high-temperature water vapor corrosion resistant coating

A technology for corrosion coating and cladding tube, which is applied in the field of high temperature water vapor corrosion resistant coating for the surface of zirconium alloy cladding tube in nuclear power plants and its preparation, which can solve the problems of inability to achieve and achieve the effect of good protection effect.

Pending Publication Date: 2022-05-06
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0009] Faced with the situation that the high-temperature water vapor corrosion resistance and wear resistance of zirconium alloy cladding tubes need to be improved urgently, although some researchers have improved their related properties, they cannot achieve a significant improvement in both properties at the same time

Method used

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  • High-temperature water vapor corrosion resistant coating for surface of zirconium alloy cladding tube of nuclear power plant and preparation method of high-temperature water vapor corrosion resistant coating
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preparation example Construction

[0031] The present invention also provides a method for preparing a high-temperature water vapor corrosion-resistant coating on the surface of a zirconium alloy cladding tube of a nuclear power plant, comprising the following steps:

[0032] S1. Pretreatment: Use alcohol, acetone and other cleaning agents to clean the zirconium alloy cladding tube to remove surface dirt, perform sandblasting treatment, and seal the cladding tube after drying;

[0033] S2. Coating the bonding layer 2: setting the bonding layer 2 on the surface of the zirconium alloy cladding tube substrate 1 by magnetron sputtering, multi-arc ion plating, thermal spraying, cold spraying, and 3D laser coating;

[0034] S3. Coating the overlapping composite film layer 3: coating the overlapping composite film layer 3 on the surface of the zirconium alloy cladding tube substrate 1 located on the bonding layer 2 by using magnetron sputtering, multi-arc ion plating, and atomic layer deposition.

[0035] Through the ...

Embodiment 1

[0037] Prepare metal Cr on the surface of the zirconium alloy cladding tube as the bonding layer 2, and the thickness of this layer is 2 μm; prepare Cr / Cr 3 C 2 Overlapping layers, the layer thickness is 20μm, in which the Cr phase layer is equiaxed crystal morphology, each layer thickness is 60nm, Cr 3 C 2 The thickness of each phase layer is 40nm.

[0038] The characteristics in the embodiment of the present invention are: 1, adopt Cr as bonding layer 2, this layer can buffer zirconium alloy and Cr 3 C 2 The difference in thermal expansion coefficient between them can enhance the bonding performance of the coating and reduce the risk of coating cracking and peeling; 2. Cr / Cr 3 C 2 The overlapping layer is 20μm, in which the Cr phase is 60nm per layer, and the Cr phase 3 C 2 Each layer is 40nm, and this embodiment can form 200 layers of dense Cr equiaxed crystal film layers. This structure can greatly reduce the formation of oxygen channels and enhance the ability to r...

Embodiment 2

[0041] Metal Nb is prepared on the surface of the zirconium alloy cladding tube as the bonding layer 2, and the thickness of the layer is 1 μm; the Cr / Si overlapping composite film layer 3 is prepared, and the thickness of the layer is 20 μm, wherein each layer of the Cr phase layer is 60 nm, and the Si phase layer 40nm per layer.

[0042] The characteristics in the embodiment of the present invention are: 1. Utilize the similar thermal expansion coefficients of Cr, Zr, and Nb, and adopt Nb as the bonding layer 2 to slow down the difference in thermal expansion coefficient between the zirconium alloy and the metal Cr, and enhance the coating bonding performance. Reduce the risk of coating cracking and peeling; 2. In the Cr / Si overlapping layer, Cr maintains equiaxed crystal morphology, which hinders the formation of oxygen channels. In this embodiment, the thickness of a group of Cr phase layer and Si phase layer is 100nm. Therefore, 200 layers of high-density Cr films can be ...

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Abstract

The invention belongs to the technical field of nuclear fuel, and particularly discloses a high-temperature water vapor corrosion resistant coating for the surface of a zirconium alloy cladding tube of a nuclear power plant and a preparation method of the high-temperature water vapor corrosion resistant coating. The surface of the zirconium alloy cladding tube base body is coated with a bonding layer, and the surface of the bonding layer is coated with an overlapped composite film layer. According to the invention, the overlapped composite film layers are arranged, and three film layer structures of a metal / metal overlapped composite film layer, a metal / ceramic overlapped composite film layer and a ceramic / ceramic overlapped composite film layer can be formed through preferential matching among materials, and the three film layer structures have respective advantages; particularly, when a material with excellent oxygen diffusion prevention performance is selected as the film layer, the optimal protection effect is achieved, and therefore the purpose of resisting high-temperature water vapor corrosion is achieved.

Description

technical field [0001] The invention relates to the technical field of nuclear fuel, in particular to a high-temperature water vapor corrosion-resistant coating for the surface of a zirconium alloy cladding tube of a nuclear power plant and a preparation method thereof. Background technique [0002] Light water reactors are the main reactor type of nuclear power plants, using rod-shaped nuclear fuel elements (hereinafter referred to as "fuel rods"). Fuel rods consist of short cylindrical UO 2 Composed of fuel pellets, zirconium alloy cladding, end plugs, compression springs in the air storage chamber, etc., there is a certain gap between the fuel pellets and the cladding, and the fuel element is filled with inert gas, such as figure 1 as shown, figure 1 Middle: 1. End plug, 2. Zirconium alloy cladding, 3. Compression spring, 4. Short cylindrical UO 2 fuel pellets. [0003] Following the Fukushima nuclear power plant disaster in 2011, in order to improve the safety of nuc...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C23C28/00C23C28/02G21C3/07
CPCC23C28/40C23C28/027C23C28/324C23C28/322C23C28/321C23C28/34G21C3/07Y02E30/30
Inventor 李崇崔严光卢俊强陆辉陈小强林基伟
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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