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High-temperature gas cooled reactor end face sealing suction gun device

A high-temperature gas-cooled reactor and end-face sealing technology, which is applied to measuring devices, greenhouse gas reduction, fluid tightness testing, etc., can solve problems such as operating environment, structural tube sheet structure differences, etc., to reduce consumption time and reduce Effect of Radiation Dose

Pending Publication Date: 2020-09-18
CHINA NUCLEAR POWER OPERATION TECH +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0002] The high-temperature gas-cooled reactor is an advanced unit independently developed by my country using a new generation of nuclear power technology. The inspection technology and inspection equipment of the steam generator heat transfer tube are the direction that needs to be vigorously developed in the future, because its steam generator is completely different from the conventional pressurized water reactor. , the operating environment, structure, especially the tube-sheet structure are all different, and there is currently no corresponding testing technology and special testing equipment

Method used

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  • High-temperature gas cooled reactor end face sealing suction gun device
  • High-temperature gas cooled reactor end face sealing suction gun device
  • High-temperature gas cooled reactor end face sealing suction gun device

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Embodiment Construction

[0045] The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.

[0046] figure 1 It is a schematic diagram of a high-temperature gas-cooled reactor end face sealing sniffing lance device according to an exemplary embodiment. Such as figure 1 As shown, the high-temperature gas-cooled stack end face sealing sniffing device may include: a positioning assembly 13, a rotating assembly 14, a lifting assembly 12, at least one sniffing assembly 11 and a bracket 17;

[0047] Generally speaking, such as figure 2 and image 3 As shown, the installation form of the throttling assembly at the feedwater inlet of the steam generator is composed of a throttling assembly 20 and an anti-loosening assembly. There are two types of installation with fixing nuts and without fixing nuts). The loosening plate can be arranged on the lower surface of the tube sheet 24. Due to the existence of the anti-loosening plate ...

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Abstract

The invention belongs to the technical field of nuclear power maintenance, and particularly relates to a high-temperature gas cooled reactor end face sealing suction gun device. According to the embodiment of the invention, the position of at least one suction gun assembly is adjusted through a rotating assembly and a lifting assembly, so that the suction gun opening structure of the suction gun assembly can be flexibly aligned with the end surface of a throttling assembly, so that helium leakage detection operation is realized. Due to the mode that the suction gun opening structure is directly in butt joint with the end face of the throttling assembly, the air leakage influence caused by a gap between the throttling assembly and an anti-loosening clamping ring is avoided, therefore, the throttling assembly, an anti-loosening plate, the anti-loosening clamping ring and a fixing nut do not need to be disassembled during helium leakage detection, the time consumed by personnel at the manhole of the evaporator is greatly shortened, and the irradiation dose of the personnel is reduced.

Description

technical field [0001] The invention belongs to the technical field of nuclear power maintenance, and in particular relates to a high-temperature gas-cooled reactor end face sealing suction gun device. Background technique [0002] The high-temperature gas-cooled reactor is an advanced unit independently developed by my country using a new generation of nuclear power technology. The inspection technology and inspection equipment of the steam generator heat transfer tube are the direction that needs to be vigorously developed in the future, because its steam generator is completely different from the conventional pressurized water reactor. , their operating environments and structures, especially the tube-sheet structure, are different, and there is currently no corresponding testing technology and special testing equipment. The structural form of the heat transfer tube of the steam generator of the high temperature gas-cooled reactor is also different from that of the convent...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/017G01M3/22
CPCG01M3/222G21C17/017Y02E30/30
Inventor 高厚秀汪兆军孙海漩王庆武朱兴华贾晶晶
Owner CHINA NUCLEAR POWER OPERATION TECH
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