Reactor pressure vessel lower sealing head surfacing welding layer detection tool and method

A pressure vessel and detection tool technology, applied in the field of nuclear power plant maintenance, can solve the problems of reduced service life of the vessel, thinning of the thickness of the surfacing layer, damage, etc. The effect of collision risk and arm-folding difficulty

Pending Publication Date: 2020-06-30
RES INST OF NUCLEAR POWER OPERATION +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Due to the extrusion and wear of the surface, deep pits are formed, resulting in the thinning or disappearance of the surfacing layer
Under the operating conditions of high temperature, high pressure and high radiation, these wear areas are prone to harmful defects due to stress concentration, reducing the service life of the container

Method used

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  • Reactor pressure vessel lower sealing head surfacing welding layer detection tool and method
  • Reactor pressure vessel lower sealing head surfacing welding layer detection tool and method
  • Reactor pressure vessel lower sealing head surfacing welding layer detection tool and method

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Embodiment Construction

[0036] Below in conjunction with accompanying drawing and specific embodiment this patent is described in detail:

[0037] It mainly includes the following technologies:

[0038] 1. Terminal monitoring technology

[0039] like figure 1 As shown, the terminal monitoring device includes: a connection block, a camera 1 , and an adapter base 2 . The distance between the two rows of penetrating parts in the surfacing layer area of ​​the lower head of the reactor pressure vessel is 200.3 mm, and the vertical heights are not completely consistent. Due to the influence of the J-shaped weld, the detection range is relatively small. The detection environment is complex and the light is weak. The monitoring method for the detection of other parts of the pressure vessel relies on the monitoring on both sides of the central box of the robot or the monitoring of the long rod camera. Both monitoring methods are far away and it is difficult to ensure long-term real-time monitoring. collis...

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PUM

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Abstract

The invention is mainly applied to the field of nuclear power station maintenance, and particularly relates to a reactor pressure vessel lower sealing head surfacing welding layer detection tool and method. In the prior art, harmful defects are easily generated due to stress concentration in wear areas of a reactor pressure vessel so as to reduce the service life of the vessel, and defect detection needs to be performed on the wear areas. The tool comprises a linear telescopic device and a tail end monitoring device, wherein the linear telescopic device is connected with the tail end monitoring device, and the tail end monitoring device is integrally located below the linear telescopic device. The invention discloses a reactor pressure vessel lower sealing head surfacing welding layer detection method, which specifically comprises the steps of detection sensitivity setting, device connection, ultrasonic eddy current detection and ultrasonic defect quantification. According to the invention, the defect detection of the worn area of the reactor pressure vessel can be effectively realized, the working efficiency is improved, and the operation cost is reduced.

Description

technical field [0001] The invention is mainly used in the field of maintenance of nuclear power plants, and in particular relates to a detection tool and method for the surfacing layer of the lower head of a reactor pressure vessel. Background technique [0002] The reactor pressure vessel is a key component of a nuclear reactor and belongs to the nuclear primary component. During the operation of a nuclear power plant, the reactor pressure vessel is mainly loaded with the reactor core and high-temperature and high-pressure coolant, and it is required to ensure the integrity of the structure under various working conditions. During pre-service installation and commissioning of reactor pressure vessels or during in-service operation, due to improper operation or the impact of high-temperature, high-pressure, and high-turbulence water flow, other internal components will fail and cause impact wear on the inner wall of the vessel, resulting in the formation of various sizes. ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/01
CPCG21C17/01Y02E30/30
Inventor 林百涛张运平尹鹏丁松王羽翀张志义蔡家藩杨丽军陈姝王玉倩金坤石磊李可
Owner RES INST OF NUCLEAR POWER OPERATION
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