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Method for preparing composite ceramic coating on zirconium alloy cladding

A technology of composite ceramics and zirconium alloys, applied in the direction of metal material coating process, coating, surface reaction electrolytic coating, etc., can solve the problems of reducing the neutron absorption efficiency of nuclear fuel, nuclear fuel reaction system pollution, etc., and achieve good anti-corrosion High-temperature water vapor corrosion performance, excellent interfacial bonding, and uniform thickness

Pending Publication Date: 2019-02-19
GUANGDONG INST OF NEW MATERIALS
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Problems solved by technology

However, this method is not suitable for the combination of YSZ coating and zirconium alloy cladding, because the introduction of the metal transition layer increases the unnecessary heavy element layer, which will greatly reduce the neutron absorption efficiency of nuclear fuel and cause nuclear fuel The reaction system is polluted, so how to realize the effective combination of zirconium alloy cladding and YSZ coating without introducing a metal transition layer is a technical problem

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  • Method for preparing composite ceramic coating on zirconium alloy cladding
  • Method for preparing composite ceramic coating on zirconium alloy cladding

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preparation example Construction

[0019] A method for preparing a composite ceramic coating for a zirconium alloy cladding, comprising:

[0020] The composite treatment process of plasma electrolytic oxidation and atmospheric plasma spraying is sequentially performed on the zirconium alloy cladding.

[0021] Further, in a preferred embodiment of the present invention, the plasma electrolytic oxidation treatment process for the zirconium alloy cladding specifically includes:

[0022] Put the degreased and degreased zirconium alloy cladding tube into a stainless steel tank containing electrolyte for plasma electrolytic oxidation treatment, and generate a zirconia ceramic film bottom layer in situ on the surface of the zirconia cladding.

[0023] Specifically, after plasma electrolytic oxidation and atmospheric plasma spraying, ZrO with a thickness of 5 to 120 μm can be generated in situ on the surface of the zirconia cladding after plasma electrolytic treatment. 2 Ceramic bottom layer, and a 50-200um thick YSZ ...

Embodiment 1

[0036] figure 1 Preparation of ZrO on the surface of the zirconium alloy cladding provided for this example 2 - Microscopic morphology of YSZ composite ceramic layer. see figure 1 , the present embodiment provides a method for preparing a composite ceramic coating for a zirconium alloy cladding, the following steps of cladding:

[0037] S1: Put the degreased and degreased Zr4 alloy cladding tube into a stainless steel tank containing electrolyte for plasma electrolytic oxidation treatment. The positive voltage of electrolytic oxidation treatment is 400V, and the duty cycle is 30%; Duty ratio 50%; frequency 800Hz, bath temperature 30°C, treatment time 30 minutes;

[0038] Among them, the electrolyte composition of plasma electrolytic oxidation treatment is: sodium polyphosphate 30g / L, sodium silicate 10g / L, sodium aluminate 10g / L, sodium oxalate 30g / L, sodium hydroxide 2g / L and ethylene glycol Disodium amine tetraacetate 2g / L;

[0039] S2: Atmospheric plasma spraying YSZ c...

Embodiment 2

[0042] figure 2 It is the appearance appearance of the composite ceramic coating obtained by using Examples 2, 3, and 4 in the same zirconium alloy cladding tube. see figure 2 , the present embodiment provides a method for preparing a composite ceramic coating for a zirconium alloy cladding, the following steps of cladding:

[0043] S1: Put the degreased and degreased M5 alloy cladding tube into the stainless steel tank containing the electrolyte for plasma electrolytic oxidation treatment. The positive voltage of electrolytic oxidation treatment is 300V, and the duty cycle is 25%; Duty ratio 25%; frequency 500Hz, bath temperature 30°C, treatment time 15 minutes;

[0044] Among them, the electrolyte composition of plasma electrolytic oxidation treatment is: sodium polyphosphate 20g / L, sodium silicate 40g / L, sodium aluminate 30g / L, sodium oxalate 20g / L, sodium hydroxide 2g / L and ethylene glycol Disodium amine tetraacetate 2g / L;

[0045] S2: Atmospheric plasma spraying YSZ...

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Abstract

The invention discloses a method for preparing a composite ceramic coating on zirconium alloy cladding, and relates to the technical field of metal surface treatment. The method comprises a compositetreatment technology of plasma electrolytic oxidation and atmospheric plasma spraying performed in sequence on the zirconium alloy cladding; a ZrO2 ceramic bottom layer 5 to 120 Mum thick is generatedin situ on the surface of the zirconium alloy cladding after the zirconium alloy cladding is treated by plasma electrolytic oxidation, and a YSZ (Yttria-Stabilized Zirconia) ceramic surface layer 50to 200 Mum thick is formed after plasma spraying. By applying the technical solution, the ZrO2 / YSZ composite ceramic coating can be prepared in situ on the surface of the zirconium alloy cladding, andthe obtained composite ceramic coating is good in interface bonding, even in thickness and compact in structure, and has good anti-corrosion property and wear-resisting property and high steam corrosion resistance; and a metal transition layer is not introduced, but efficiency of absorbing neutrons by a nuclear fuel cannot be reduced, and a nuclear fuel reaction system cannot be polluted.

Description

technical field [0001] The invention relates to the technical field of metal surface treatment, and in particular to a method for preparing a composite ceramic coating for zirconium alloy cladding. Background technique [0002] Zirconium alloy cladding is a key material used in nuclear power reactor cores. It is called the "first safety barrier" of nuclear reactors. Its stable performance and improved life are the key to ensuring the safety and reliability of nuclear reactor cores. After the Fukushima nuclear accident in 2011, when a power outage accident occurred in the entire plant under extreme conditions beyond the design basis, the safety and reliability of the existing nuclear fuel system was flawed, so develop a new nuclear fuel system or improve the accident tolerance of existing nuclear fuel structural materials Sex has become the research focus and development trend in this field. Accident tolerant fuels (Accident tolerant fuels, ATF) is a new generation of nuclea...

Claims

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Application Information

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IPC IPC(8): C23C4/134C23C4/11C25D11/26C23C28/04
CPCC23C4/11C23C4/134C23C28/04C25D11/26
Inventor 张吉阜刘敏代明江邓春明邓畅光宋进兵陈兴驰
Owner GUANGDONG INST OF NEW MATERIALS
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