Accident fault tolerance nuclear fuel cladding coating for zirconium alloy surface

Abstract

The invention discloses an accident fault tolerance nuclear fuel cladding coating for a zirconium alloy surface, and belongs to the technical field of accident fault tolerance nuclear fuel cladding coating. A first protection layer is mounted on the outer surface of zirconium alloy, a second protection layer is mounted on the outer surface of the first protection layer, and a third protection layer is mounted on the outer surface of the second protection layer. According to the accident fault tolerance nuclear fuel cladding coating for the zirconium alloy surface, through advantages of a laminated construction and compositing multiple coatings, a Cr coating can effectively improve the attaching force between the coating and a zirconium alloy substrate, meanwhile, the accident fault tolerance protection capacity is achieved, a CrTiAlN coating has the good high-temperature oxidation resistance property, and can be normally used in the normal state, and the high-temperature working condition, a CrN coating has the good corrosion resistance, and meets the long-term service under the hot water corrosion working condition, and the laminated composite protection coating can comprehensively improve the stability and the safety of accident fault tolerance nuclear fuel cladding.

Description

technical field [0001] The invention relates to the technical field of accident-tolerant nuclear fuel cladding coatings, in particular to an accident-tolerant nuclear fuel cladding coating for zirconium alloy surfaces. Background technique [0002] Nuclear power is a source of electricity with large-scale power generation, high economic benefits, and sustainable development. It has been adopted by many countries in the world. The research on cladding materials in nuclear reactors has always been a focus. At present, the most widely used cladding The material is zirconium alloy, because it has excellent corrosion resistance, good anti-irradiation growth characteristics and moderate mechanical properties, etc., but one of the most important problems in the application of zirconium alloy in the reactor is in the case of a loss of water accident in the reactor Under high temperature conditions, the temperature of the zirconium tube rises sharply. When the temperature is greater ...

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Problems solved by technology

[0005] Aiming at the deficiencies of the prior art, the present invention provides an accident-tolerant nuclear fuel cladding coating for the surface of zirconium alloys, which solves the problem of lack of comprehensive protective performance of the accident-tolerant nuclear fuel cladding coating

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