The robot mag surfacing process of the corrosion-resistant layer of the inlet and outlet of the pressure vessel of the civilian nuclear reactor

A technology for civilian nuclear reactors and pressure vessels, which is applied in the field of surfacing welding technology for civil nuclear reactor pressure vessels, to achieve the effect of improving the stability of welding quality and improving welding efficiency

Active Publication Date: 2020-01-14
上海电气核电集团有限公司
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  • Description
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Problems solved by technology

[0006] The purpose of the present invention is to provide the MAG surfacing welding process of the corrosion-resistant layer robot for the inlet and outlet of the civil nuclear reactor pressure vessel, which can replace the current manual arc welding used in the saddle-shaped end face corrosion-resistant layer surfacing, overcome the aforementioned welding quality problems and improve welding efficiency

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  • The robot mag surfacing process of the corrosion-resistant layer of the inlet and outlet of the pressure vessel of the civilian nuclear reactor
  • The robot mag surfacing process of the corrosion-resistant layer of the inlet and outlet of the pressure vessel of the civilian nuclear reactor
  • The robot mag surfacing process of the corrosion-resistant layer of the inlet and outlet of the pressure vessel of the civilian nuclear reactor

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[0019] The present invention will be further described below in conjunction with specific embodiments and accompanying drawings. In the following description, more details are set forth in order to fully understand the present invention, but the present invention can obviously be implemented in a variety of other ways different from this description, Those skilled in the art can make similar promotions and deductions based on actual application situations without violating the connotation of the present invention, so the content of this specific implementation manner should not limit the protection scope of the present invention.

[0020] It should be noted that these and other subsequent drawings are only examples, which are not drawn according to the same scale, and should not be taken as limitations on the protection scope of the actual claims of the present invention. In addition, transformation manners in different implementation manners may be properly combined.

[0021]...

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Abstract

The invention provides a robot MAG overlay welding process for a civil nuclear reactor pressure vessel access adapter pipe anti-corrosion layer. The robot MAG overlay welding process for the civil nuclear reactor pressure vessel access adapter pipe anti-corrosion layer comprises the steps of welding at least two welding layers, adopting low alloy steel as base metal and a welding material as austenitic stainless steel, providing a tail drag protection gas hood for a welding gun, providing a protection gas for the tail drag protection gas hood, and enabling to eh protection gas to cover a welding pass adjacent to a molten pool, wherein the protection gas is He+CO2+Ar, and the dilution rate is controlled to be smaller than 27 percent. According to the robot MAG overlay welding process provided by the invention, an overlay welding layer has no defects such as air holes, microcracks, and incomplete fusion between passes.

Description

technical field [0001] The invention relates to a welding process, in particular to a surfacing welding process for civil and nuclear reactor pressure vessels. Background technique [0002] At present, the surfacing welding of the saddle-shaped end face corrosion-resistant layer of the reactor pressure vessel inlet and outlet of the main equipment of the domestic nuclear island is mainly performed by manual electrode arc welding. There is no public literature about the application of robotic MAG (melting electrode arc welding) surfacing welding technology in the civil nuclear field. On the one hand, manual electrode arc welding has low welding efficiency, and on the other hand, the stability of weld quality is poor. [0003] The MAG surfacing process has been applied in non-civilian nuclear fields, but its welding quality requirements are lower than those in civil nuclear fields, so it cannot be directly applied to civil nuclear fields. [0004] In practice, the inventor f...

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B23K9/04B23K9/173
CPCB23K9/04B23K9/173
Inventor 杨乘东张茂龙袁骞茹祥坤盛旭婷唐伟宝
Owner 上海电气核电集团有限公司
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