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High-temperature gas cooled reactor heat transfer tube inspection device

A high-temperature gas-cooled reactor and inspection device technology, which is applied in the direction of reducing greenhouse gases, monitoring of reactors and nuclear reactors, etc., can solve the problems of difficult non-destructive testing of heat transfer tubes, and achieve the effect of compact and lightweight structure.

Pending Publication Date: 2019-04-19
RES INST OF NUCLEAR POWER OPERATION +2
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AI Technical Summary

Problems solved by technology

[0003] In order to solve the problem that non-destructive testing of steam generator heat transfer tubes in high temperature gas-cooled reactors is difficult, a helium mass spectrometry inspection device that can be applied to steam generator heat transfer tubes in high temperature gas-cooled reactors is invented. The inspection device can cover steam generators All tube plate holes to realize automatic inspection of heat transfer tubes

Method used

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  • High-temperature gas cooled reactor heat transfer tube inspection device
  • High-temperature gas cooled reactor heat transfer tube inspection device
  • High-temperature gas cooled reactor heat transfer tube inspection device

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Embodiment Construction

[0032] The present invention will be further described below in conjunction with the accompanying drawings and embodiments.

[0033] According to the structural characteristics of the high temperature gas-cooled reactor steam generator, the main actions of the inspection device are divided into circular motion, radial expansion and vertical lifting. This cylindrical coordinate structure makes full use of the axisymmetric features of the tube sheet and the water chamber. The inspection device realizes circular motion through the slewing mechanism, and uses the guide rail to realize radial linear sliding. The combination of the two actions can drive the suction gun to cover the entire tube sheet distribution area of ​​holes. The vertical lift is mainly used to control the action of the suction gun.

[0034] Such as Figure 1 to Figure 7As shown, a high-temperature gas-cooled reactor heat transfer tube inspection device adopts a modular design and mainly includes a suction gun ...

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Abstract

The invention belongs to the technical field of non-destructive testing and maintenance of steam generator heat transfer tubes and similar heat exchange equipment, and particularly relates to a high-temperature gas cooled reactor heat transfer tube inspection device, which aims to solve the problem that it is difficult to implement nondestructive testing of a high-temperature gas cooled reactor heat transfer tube. The invention is characterized in that the device comprises a suction gun device, a guide rail component, a swing mechanism and an outrigger mechanism. The suction gun device and theguide rail component are connected by a quick-change structure. By stirring a rotating chuck of the quick-change structure, rapid locking between the suction gun device and the guide rail component and their rapid connection can be realized. The outrigger installation mechanism adopts a foldable form and is convenient for the staff to carry.

Description

technical field [0001] The invention belongs to the technical field of non-destructive detection and maintenance of steam generator heat transfer tubes and similar heat exchange equipment, and in particular relates to a high-temperature gas-cooled reactor heat transfer tube inspection device. Background technique [0002] The high temperature gas-cooled reactor is a new generation of nuclear power reactors. Compared with the operating reactors, the structure of the steam generator heat exchange tube of the high temperature gas-cooled reactor is quite different, and the operating environment is very different. The traditional heat exchange tube inspection method has Cannot meet the inspection requirements. The structure of the heat exchange tube of the high temperature gas-cooled reactor steam generator is a spiral coil with a small bending radius. There is a throttling assembly at the main feed water inlet. The sealing of the water chamber tube sheet. The size of the envir...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/017
CPCG21C17/017Y02E30/30
Inventor 高厚秀汪兆军陈磊聂炜超杨帆韩捷吴东栋
Owner RES INST OF NUCLEAR POWER OPERATION
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