Preparation method of surface coating of zirconium alloy cladding and surface coating

Abstract

The invention provides a preparation method of a surface coating of a zirconium alloy cladding, and further provides the surface coating. The preparation method is characterized in that a carbide target material is adopted to form a carbide coating on a zirconium alloy matrix. The preparation method comprises the steps that mechanical grinding and polishing treatment are carried out on the zirconium alloy matrix; the zirconium alloy matrix is placed in a solution composed of acetone and deionized water to be subjected to ultrasonic cleaning; the zirconium alloy matrix is subjected to low-temperature drying treatment; the carbide target material is subjected to sputtering sintering through a radio frequency magnetron sputtering method, sputtering power is 1200 W or below, the bias range is0 V to 1000 V, and a carbide coating is formed; the zirconium alloy matrix on which the carbide coating is formed is taken out of a magnetron sputtering instrument, and thermal treatment is carried out under an argon environment for 1 h to 3 h at the temperature of 500 DEG C to 700 DEG C; and the zirconium alloy cladding on which the carbide coating is formed is subjected to inspection. Accordingto the preparation method of the surface coating of the zirconium alloy cladding, corrosion resistance and oxidization resistance of the zirconium alloy cladding can be improved.

Description

technical field [0001] The invention relates to the technical field of surface treatment, in particular to a method for preparing a surface coating of a zirconium alloy cladding and a surface coating. Background technique [0002] Nuclear fuel cladding is the first protective barrier of a nuclear reactor, and its safety is of paramount importance. As far as its working condition is concerned, because one side is close to the high-temperature nuclear fuel pellet part, and the other side is in contact with the coolant under high temperature and high pressure (for example, the temperature is between 280-350°C and the pressure is between 10-16MPa Inter-) contact, so during use, on the side close to the core block, the expanded core block will generate strain with the cladding (PCI, Pellet-Cladding interaction), resulting in stress corrosion cracking (SCC, Stress Corrosion Cracking) of the cladding ), while on the side close to the coolant, it will be corroded by the coolant. T...

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Problems solved by technology

However, due to the high temperature environment, especially in the loss of coolant accident or loss of water accident (LOCA, Loss of Coolant Accident) conditions, the zirconium alloy on the water side will undergo severe corrosion and hydrogen absorption, resulting in brittle fracture of the cladding tube Phenomenon

For example, in the Fukushima accident, due to the loss of water in the core and the temperature rising to about 1200°C, the intense heat release of the fuel rod zirconium alloy cladding and water vapor will greatly accelerate the process of the accident, which not only directly releases a large amount of heat, but also causes the fuel element to explode rapidly. As the temperature rises, a large amount of hydrogen is also produced, causing serious consequences such as hydrogen explosion and leakage of radioactive substances.

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