Front-end probe mechanism of reactor pressure vessel checking machine
Patent Information
- Authority / Receiving Office
- CN ยท China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- CGNPC INSPECTION TECH
- Publication Date
- 2010-11-24
- Estimated Expiration
- Not applicable ยท inactive patent
Smart Images
Figure 1 Figure 2 Figure 3
Abstract
Description
technical field
[0001] The invention relates to a nuclear power plant reactor pressure vessel weld seam detection device. Background technique
[0002] The lower part of the nuclear reactor pressure vessel is welded by a cylindrical body 100 and a hemispherical lower head 200, such as figure 1 As shown, therefore, there is a weld 300 at the connection between the two under the pressure vessel. According to the relevant inspection specifications of nuclear power plants, the area of โโ50mm on both sides of the weld ( image 3 (shown in the shaded part in the middle) for flaw detection inspection. At the same time, the surfacing layer on the surface also needs to be scanned with the weld as the center line and 250 mm on both sides. In the prior art, there are ultrasonic principles for detection The principle of the inspection machine is to extend the probe into the bottom of the pressure vessel for scanning. Since the area to be scanned is a spherical surface, the installation...