Composite high-temperature anti-oxidation coating of graphite material for nuclear reactor and preparation method of composite high-temperature anti-oxidation coating

A technology of high-temperature anti-oxidation and graphite materials, which is applied in the field of nuclear applications, can solve the problems of high sintering temperature and poor oxidation resistance of coatings, and achieve the effects of high bonding strength, strong anti-oxidation ability and excellent anti-oxidation performance

Active Publication Date: 2021-10-22
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] For the preparation of anti-oxidation coatings on the surface of graphite materials for nuclear reactors, the coatings prepared by the existing preparation methods have problems such as poor oxidation resistance and high sintering temperature.

Method used

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  • Composite high-temperature anti-oxidation coating of graphite material for nuclear reactor and preparation method of composite high-temperature anti-oxidation coating
  • Composite high-temperature anti-oxidation coating of graphite material for nuclear reactor and preparation method of composite high-temperature anti-oxidation coating
  • Composite high-temperature anti-oxidation coating of graphite material for nuclear reactor and preparation method of composite high-temperature anti-oxidation coating

Examples

Experimental program
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Effect test

Embodiment 1

[0057] A preparation method of a composite high-temperature anti-oxidation coating of a graphite material for a nuclear reactor, the preparation method comprising the steps of:

[0058] Preparation of embedding powder

[0059] Embedding powder: Weigh 30g of 300μm Si powder, with a mass fraction of 60%; 10g of 300μm SiC powder, with a mass fraction of 20%; 300μm of Al 2 o 3 Powder 5g, mass fraction is 10%; Reactor uses natural graphite powder 5g, mass fraction is 10%;

[0060] Put the above mixed powders into ball mill jars respectively, add 100ml of alcohol, and adjust the speed of ball mill to 300rpm; after ball milling and mixing for 12 hours, take it out and dry in a vacuum oven at 50°C for 24 hours for later use.

[0061] Preparation of molten salt powder

[0062] Molten salt powder: Weigh 2.5g of 300μm Ti powder with a mass fraction of 20%; 4.4g of a purity of 98% NaCl powder with a mass fraction of 35.2%; 5.6g of a purity of 98% of KCl powder with a mass fraction of 4...

Embodiment 2-4

[0071] The preparation methods of Examples 2-4 refer to Examples, and the parameters of each step are shown in Table 1.

[0072] Table 1

[0073]

[0074] In the preparation methods of Examples 2-4, the amount of Ti powder used in the molten salt process is different, resulting in the Ti-rich layer of the composite coating being generated containing different phases and the contents of different phases are different. The composite coating composition of each embodiment as follows:

example 2

[0075] Example 2: Ti-rich layer (Ti 3 SiC 2 and TiC), SiC layer (SiC), transition layer (SiC and graphite);

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Abstract

The embodiment of the invention relates to the technical field of nuclear application, in particular to a composite high-temperature anti-oxidation coating of a graphite material for a nuclear reactor and a preparation method of the composite high-temperature anti-oxidation coating. The preparation method comprises the following steps: mixing Si powder, SiC powder, Al2O3 powder and graphite powder to obtain embedding powder; embedding the graphite sample in the embedding powder to obtain an embedded sample; blending the Ti powder, NaCl and KCl to obtain molten salt powder; embedding the embedding treatment sample in molten salt powder to obtain a molten salt treatment sample; and washing and drying the sample to remove residual powder on the surface to obtain the product, wherein the sintering atmosphere during embedding is inert atmosphere, and the heat preservation time is less than or equal to 2 hours; the temperature during molten salt sintering is 700-1200 DEG C, and the heat preservation time is longer than or equal to 2 hours. According to the preparation method, an embedding method and a molten salt method are combined, so that the Ti3SiC2 / SiC composite high-temperature anti-oxidation coating is prepared on the surface of the graphite material for the nuclear reactor. The preparation temperature is low, the composite coating is high in oxidation resistance, the bonding strength between the composite coating and a graphite base material is high, and the grain size of the formed composite coating is small inside and large outside.

Description

technical field [0001] The invention relates to the technical field of nuclear applications, in particular to a composite high-temperature anti-oxidation coating of graphite materials used in nuclear reactors and a preparation method thereof. Background technique [0002] Graphite materials have outstanding advantages such as high temperature resistance, small neutron absorption cross-section, stable chemical properties, and excellent high-temperature mechanical properties. They are widely used in high-temperature fields such as nuclear reactors, aerospace, electronics, and machinery. The biggest disadvantage of graphite material is that it is very easy to react with oxidizing gas and fail when it is above 500°C, and it is very sensitive to the oxidizing atmosphere in the use environment. Carbon materials also face the same problem. In addition, due to process limitations, it is difficult to prepare coatings on the surface of graphite materials with irregular shapes, which ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C04B41/89
CPCC04B41/89C04B41/52C04B41/009C04B35/522C04B41/5059C04B41/4545C04B41/5001C04B41/5057Y02E30/30
Inventor 杨辉赵宏生张凯红刘小雪王桃葳李自强高原刘兵唐亚平
Owner TSINGHUA UNIV
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