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Method for improving toughness of zirconium alloy cladding material

A cladding material and zirconium alloy technology, which is applied in the fields of reactor fuel elements, climate sustainability, nuclear power generation, etc., can solve the problem of increasing the risk of damage to the zirconium alloy cladding and increasing the radial hydride precipitation in the zirconium alloy cladding. and other problems, to achieve the effect of easy implementation, recovery of toughness, and simple operation

Active Publication Date: 2019-07-26
CHINA NUCLEAR POWER ENG CO LTD
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Problems solved by technology

The above-mentioned operations on the spent fuel assembly will cause it to go through multiple loading and unloading processes, which will inevitably be accompanied by a temperature cycle process, which will intensify the precipitation of radial hydrides in the zirconium alloy cladding of the spent fuel assembly, and will increase the amount of the zirconium alloy cladding Risk of shell breakage

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  • Method for improving toughness of zirconium alloy cladding material
  • Method for improving toughness of zirconium alloy cladding material

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Embodiment Construction

[0045] The present invention will be further described below in conjunction with the accompanying drawings and embodiments.

[0046] Principle of the method:

[0047] The solubility of hydrogen in the zirconium alloy cladding of the spent fuel assembly decreases as the temperature decreases ( figure 1), precipitated from the solid solution state to the solid state of the compound. Hydrogen compounds exist in two forms: radial hydrides and ring hydrides. One of the conditions for the generation of hydrides in two different directions is the direction and magnitude of the internal stress of the zirconium alloy cladding material at the moment of precipitation. If the hoop tensile stress of the zirconium alloy cladding (usually generated by internal pressure) is higher than a certain critical value, hydrogen will be precipitated in the form of radial hydrides during cooling, and this orientation of hydrides will seriously reduce the cladding. toughness. Another hoop hydride do...

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Abstract

The invention belongs to the technical field of zirconium alloy cladding repair, and particularly relates to a method for improving the toughness of a zirconium alloy cladding material. The method isused for treating the zirconium alloy cladding of a spent fuel assembly, the method comprises the following steps of S1, maintaining the temperature of the zirconium alloy cladding at T0, and the environment pressure of the zirconium alloy cladding is increased from P0 to P1; S2, the temperature of the zirconium alloy cladding is increased from T0 to T1, and meanwhile, the ambient pressure of thezirconium alloy cladding is increased from P1 to P2; S3, keeping the temperature of the zirconium alloy ladle in an environment with the pressure of P2 and the temperature of T1, and the length of themaintaining time is T0; S4, the temperature of the zirconium alloy cladding is reduced from T1 to T0, and meanwhile, the ambient pressure of the zirconium alloy cladding is reduced from P2 to P1; andS5, maintaining the temperature of the zirconium alloy cladding at T0, and the environment pressure of the zirconium alloy cladding is reduced from P1 to P0. According to the method, the appearance geometrical structure of the spent fuel assembly is not changed, no negative influence is generated on the operation steps of the normal spent fuel assembly.

Description

technical field [0001] The invention belongs to the technical field of zirconium alloy cladding repair, and in particular relates to a method for improving the toughness of spent fuel zirconium alloy cladding materials. Background technique [0002] The spent fuel assemblies unloaded after combustion in PWR nuclear power plants, especially the spent fuel assemblies with high burnup consumption (more than 45000MWd / tU), due to the radiation damage and the precipitation of radial hydrides during the service life, the external The toughness properties of the zirconium alloy cladding decrease. During the transportation from the nuclear power plant to the intermediate storage site and the long-distance complex road conditions of the reprocessing plant, the zirconium alloy cladding may be damaged and leaked after being subjected to relatively large vibrations, causing radioactive fission gas to be released into the inner cavity of the transport container, adding The subsequent ope...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22F1/18G21C19/20
CPCC22F1/186G21C19/207Y02E30/30
Inventor 汪俊贺楷姚琳江小川申腾周潇李宁董建华卢可可张朔婷
Owner CHINA NUCLEAR POWER ENG CO LTD
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