A method for improving the toughness of spent fuel zirconium alloy cladding material

A cladding material, zirconium alloy technology, applied in reactor fuel elements, climate sustainability, reduction of greenhouse gases, etc., can solve the problem of increasing the risk of zirconium alloy cladding damage and aggravating radial hydride precipitation in the zirconium alloy cladding. Quantity and other issues, to achieve the effect of easy implementation, recovery of toughness, and increased ability to shock and impact

Active Publication Date: 2022-01-14
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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  • A method for improving the toughness of spent fuel zirconium alloy cladding material
  • A method for improving the toughness of spent fuel zirconium alloy cladding material

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Embodiment Construction

[0045] The present invention is further described below with reference to the accompanying drawings and examples.

[0046] Method principle:

[0047] The solubility of the hydrogen in the zirconium alloy shell of the lack of fuel assembly decreases as the temperature decreases as the temperature is lowered. figure 1The solid was precipitated from the solid solution to the solid state. The compound of hydrogen has two forms: the radial hydride and the ring to the hydride. One of these two different directions of hydrides is one of the internal stress directions and stress sizes of the time zirconium alloy shell material. If the ring to pull stress of the zirconium alloy cladding (usually generated by internal pressure) is higher than a certain critical value, hydrogen is precipitated in the form of a radial hydride during the cooling process, which will severely reduce the shell in the form of a radial hydride during the cooling process. Toughness. Another cyclo-hydride does not re...

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Abstract

The invention belongs to the technical field of zirconium alloy cladding repair, and specifically relates to a method for improving the toughness of zirconium alloy cladding materials, which is used for processing zirconium alloy cladding of spent fuel assemblies, including: step S1, wrapping zirconium alloy cladding The shell temperature is maintained at T 0 , and change the ambient pressure of the zirconium alloy cladding from P 0 up to P 1 ; Step S2, changing the temperature of the zirconium alloy cladding from T 0 rise to T 1 , while changing the ambient pressure of the zirconium alloy cladding from P 1 up to P 2 ; Step S3, maintaining the zirconium alloy cladding at a pressure of P2 and a temperature of T 1 In the environment, the length of maintenance time is t 0 ; Step S4, changing the zirconium alloy cladding temperature from T 1 down to T 0 , while changing the ambient pressure of the zirconium alloy cladding from P 2 down to P 1 ; Step S5, maintaining the temperature of the zirconium alloy cladding at T 0 , and change the ambient pressure of the zirconium alloy cladding from P 1 down to P 0 . This method does not change the appearance geometry of the spent fuel assembly, and does not have a negative impact on the normal operating steps of the spent fuel assembly.

Description

Technical field [0001] The present invention belongs to the field of zirconium alloy shell repair technology, and more particularly to a method for improving the toughness of a lack of fuel zirconium alloy shell material. Background technique [0002] The lack of fuel assemblies, especially high-fuel consumption (greater than 45,000 mwd / tu), which are highly fuel consumption (greater than 45,000 mwd / tu), resulting in an exterior of radioactive radiation injury and radial hydride due to the precision of radioamide in the life. The toughness performance of the zirconium alloy shell is lowered. During the complex road conditions of transporting from the nuclear power plant plant and the post-treatment plant, the zirconium alloy enclosure may damage the leakage, resulting in the release of radioactive gas release to the lumen of the transport container, plus Large subsequent operation is difficult to cause radiation damage to the public. [0003] At present, the management of nuc...

Claims

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Application Information

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Patent Type & Authority Patents(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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