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A kind of preparation method of zirconium alloy cladding surface composite coating for nuclear fuel

A surface composite, zirconium alloy technology, applied in metal material coating process, coating, vacuum evaporation plating, etc., can solve the problems of high interface stress, brittle fracture, insufficient toughness, etc., and achieve good strength and toughness matching, heat resistance Improvement of impact performance and avoidance of increased brittleness

Active Publication Date: 2021-01-26
NORTHWEST INSTITUTE FOR NON-FERROUS METAL RESEARCH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

However, the soft matrix / hard coating system composed of ceramic coating and zirconium alloy metal substrate is prone to defects such as high interfacial stress and insufficient toughness, so it is prone to brittle fracture under severe temperature changes, showing high brittleness.

Method used

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  • A kind of preparation method of zirconium alloy cladding surface composite coating for nuclear fuel
  • A kind of preparation method of zirconium alloy cladding surface composite coating for nuclear fuel

Examples

Experimental program
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Embodiment 1

[0025] This embodiment includes the following steps:

[0026] Step 1. Polish the surface of the Zr-4 alloy cladding to a mirror surface, then perform degreasing and descaling pretreatment in sequence, soak in acid solution for pickling activation, and then place it in the vacuum chamber of the vapor deposition equipment and pass it into The pressure of argon to the vacuum chamber is 5×10 -2Pa, then use the Cr ions produced by the discharge of the Cr arc target source to clean and activate the Zr-4 alloy cladding after pickling and activation; the accelerating voltage of Cr ions in the cleaning and activation process is 1200V, and the temperature in the cleaning and activation process is 200°C; the bombardment activation of Cr ions in the cleaning activation process is divided into 5 stages, and the time of continuous bombardment activation in each stage is 2min, the intermittent time is 3min, and the total time of bombardment activation is 25min;

[0027] Step 2. Adjust the p...

Embodiment 2

[0038] This embodiment includes the following steps:

[0039] Step 1. Polish the surface of the N18 zirconium alloy cladding to a mirror surface, then perform degreasing and descaling pretreatments in sequence, and soak in acid solution for pickling activation, and then place it in the vacuum chamber of the vapor deposition equipment and pass it into argon The pressure of the gas to the vacuum chamber is 1×10 -2 Pa, the Cr ions produced by the discharge of the Cr magnetron target source are used to clean and activate the N18 zirconium alloy cladding after pickling and activation; the accelerating voltage of Cr ions in the cleaning and activation process is 1000V, and the temperature in the cleaning and activation process is 150°C; the bombardment activation of Cr ions in the cleaning activation process is divided into 4 stages, and the time of continuous bombardment activation in each stage is 1min, the intermittent time is 2min, and the total time of bombardment activation is...

Embodiment 3

[0050] This embodiment includes the following steps:

[0051] Step 1. Polish the surface of the N36 zirconium alloy cladding to a mirror surface, then perform degreasing and descaling pretreatments in sequence, and soak in acid solution for pickling activation, and then place it in the vacuum chamber of the vapor deposition equipment and pass it into argon The pressure of the gas to the vacuum chamber is 1×10 -1 Pa, then use the Cr ions generated by the discharge of the Cr magnetic filter arc target source to clean and activate the N36 zirconium alloy cladding after pickling and activation; the accelerating voltage of Cr ions in the cleaning and activation process is 1300V, and the temperature in the cleaning and activation process is 500°C; the bombardment activation of Cr ions in the cleaning activation process is divided into 10 stages, and the time of continuous bombardment activation in each stage is 1min, the intermittent time is 2min, and the total time of bombardment a...

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Abstract

The invention discloses a preparation method of a surface composite coating of a zirconium alloy cladding for nuclear fuel. The method comprises the steps as follows: step one, the zirconium alloy cladding for nuclear fuel is subjected to surface polishing, pretreatment and acid cleaning activation and then is put in a vacuum chamber of vapor deposition equipment for cleaning activation; step two,a Cr transition layer is deposited on the zirconium alloy cladding after the cleaning activation; step three, the Cr transition layer is activated; step four, a CrN layer is deposited on the activated Cr transition layer; step five, the CrN layer is activated; and step six, processes of the steps two to five are repeated, and the Cr / CrN composite coating is obtained on the surface of the zirconium alloy cladding for the nuclear fuel. The Cr transition layer is utilized to uniformly disperse residual internal stress in CrN layer deposition, toughness of the CrN layer is enhanced while high hardness of the CrN layer surface is guaranteed, the Cr / CrN composite coating with corrosion resistance, high thermal shock resistance, high toughness and good matching performance is obtained, and the requirement of the surface coating service performance of the zirconium alloy cladding under the working condition of nuclear is met.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel, and in particular relates to a method for preparing a composite coating on the surface of a zirconium alloy cladding for nuclear fuel. Background technique [0002] The explosion accident of the Fukushima nuclear power plant in Japan shows that under the conditions of the loss of water accident of the fuel element system in the nuclear reactor, the poor cooling of the core will lead to a rapid increase in the temperature of the cladding, which will accelerate the oxidation rate. When the core temperature continues to rise to 1200 ° C , the zirconium alloy cladding reacts with high-temperature water vapor and produces a large amount of hydrogen, which will cause the explosion of the core and pose a threat to the safety of the reactor. The nuclear industry is stepping up efforts to develop safe and reliable accident tolerant fuel (Accident Tolerant Fuel, referred to as ATF). ATF can greatly i...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C23C14/16C23C14/06C23C14/18C23C14/02
CPCC23C14/0021C23C14/02C23C14/021C23C14/0641C23C14/16C23C14/18
Inventor 王彦峰李争显王毅飞耿娟娟张长伟罗倩
Owner NORTHWEST INSTITUTE FOR NON-FERROUS METAL RESEARCH
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