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Method for preparing SiC coating on surface of spherical graphite material

A spherical graphite and coating technology, applied in the field of nuclear applications, can solve the problems of large particle size of coating slurry, unsatisfactory micropore impregnation, and difficult to uniform coating thickness.

Inactive Publication Date: 2015-12-09
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This method is simple in process and low in cost, but the particle size in the coating slurry is large, which is not ideal for impregnating the micropores in the matrix material; at the same time, the coating prepared by this method has a high sintering temperature, poor density, and is easy to crack. The thickness of the coating is not uniform and the surface is rough
[0011] Therefore, the current SiC coating preparation process still needs to be improved.

Method used

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  • Method for preparing SiC coating on surface of spherical graphite material
  • Method for preparing SiC coating on surface of spherical graphite material
  • Method for preparing SiC coating on surface of spherical graphite material

Examples

Experimental program
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Effect test

Embodiment 1

[0065] 1) Preparation of embedding powder

[0066] Embedding powder: Weigh 30 g of Si powder with a particle size of 300 mesh and a purity of 99.99%, 10 g of SiC powder with a particle size of 300 mesh and a purity of 99.99%, and Al with a particle size of 300 mesh and a purity of 99.99%. 2 o 3 5g of graphite powder, 5g of natural graphite powder for reactors; put the above mixed powders into ball mill tanks respectively, add 50ml of acetone, adjust the speed of ball mill to 300rpm; after ball milling for 8 hours, take out the mixture after ball milling, and place it in a vacuum at 120°C Dry in a drying oven for 2 hours, and pass the dried powder through a 300-mesh sieve to obtain the embedding powder.

[0067] 2) Sintering treatment

[0068] The sintering treatment is carried out in a high temperature graphite sintering furnace. Specifically, the processed spherical graphite material used in the reactor is buried in a graphite crucible filled with embedding powder, so that...

Embodiment 2-5

[0079] The preparation method of embodiment 2-5 is with embodiment 1, and wherein, each specific parameter sees the following table:

[0080]

[0081]

[0082] The structure and properties of the prepared SiC coating are similar to those of the SiC coating prepared in Example 1, and will not be described in detail here.

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Abstract

The invention provides a method for preparing a SiC coating on the surface of a spherical graphite material. The method comprises the steps of (1) mixing Si powder, SiC powder, Al2O3 powder and graphite powder, so as to obtain embedding powder; (2) embedding the spherical graphite material into the embedding powder, and jolt-ramming an embedded mixture, so as to obtain the embedded mixture after jolt-ramming; (3) performing sintering treatment on the embedded mixture after jolt-ramming in an argon atmosphere, so as to obtain sintering treatment products; (4) performing chemical vapor deposition on the sintering treatment products in a spouted fluidized bed in the condition that methyl trichlorosilane, hydrogen and argon are introduced, so as to form the SiC coating on the surface of the spherical graphite material. By utilizing the method, the SiC coating which has the advantages of integrity in coating, uniformity in thickness, good transitivity and high bonding strength with a substrate can be rapidly and effectively prepared on the surface of the spherical graphite material.

Description

technical field [0001] The invention belongs to the technical field of nuclear application, and in particular relates to a method for preparing a SiC coating on the surface of a spherical graphite material. Background technique [0002] Graphite is one of the foundations on which nuclear reactors are built. It is not only the main component of reactor structural support materials and shielding materials, but also the matrix material of fuel elements in fourth-generation high-temperature air-cooled reactors. Therefore, the research on graphite materials is of great importance to the safety and security of reactors. Development is very important. Graphite materials have outstanding advantages such as high temperature resistance, small neutron absorption cross-section, stable chemical properties, and excellent high-temperature mechanical properties. The biggest disadvantage is that it is easy to react with oxidizing gases above 500°C and fail. [0003] Graphite materials are w...

Claims

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Application Information

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IPC IPC(8): C04B41/87
Inventor 周平赵宏生李自强张凯红刘小雪刘兵唐春和
Owner TSINGHUA UNIV
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