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Automatic shifting platform for welding inspection of adapter of pressure vessel

A technology for inspection of welding seams and pressure vessels. It is used in the monitoring of nuclear reactors, reactors, and nuclear power generation. Control, smooth movement, and ensure the effect of safety

Active Publication Date: 2014-11-05
RES INST OF NUCLEAR POWER OPERATION +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The inspection implementation method of the supreem inspection system uses a layered plane fixed platform to realize the inspection of the reactor pressure vessel. If the inspection is carried out according to the previous inspection system, the inspection manipulator needs to be lifted out of the water frequently during the inspection process, and the positioning device of the platform needs to be disassembled and assembled. , and disassembled many times, the inspection robot arm and the positioning platform are lifted out, which increases the inspection time
In addition, frequent operations on the reactor also increase the risk of inspections, and the dose to personnel is increased

Method used

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  • Automatic shifting platform for welding inspection of adapter of pressure vessel
  • Automatic shifting platform for welding inspection of adapter of pressure vessel
  • Automatic shifting platform for welding inspection of adapter of pressure vessel

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Embodiment Construction

[0019] The present invention is described in detail below in conjunction with accompanying drawing and embodiment:

[0020] like figure 1 , figure 2 and image 3 The worm gear transmission 2 and the motor 1 are all fixedly installed in the fixed seat 8, and the worm gear transmission 2 is driven by the motor 1. Three supporting legs 9 can be evenly arranged at intervals of 120° in the horizontal circumferential direction on the outside of the fixing seat 8 as a supporting platform. The fixing seat 8 is fixedly connected with the upper end of the inner core barrel 4 through the connecting flange 11 . On the outer wall of the inner core tube 4, a linear guide rail 3 is installed along the axis direction, the inner core tube 4 is covered with an outer sleeve 5, and the screw rod 7 is arranged in the inner core tube 4, and the worm screw of the worm gear transmission device 2 at the upper end is fixedly connected to the outer sleeve. 5 bottoms are fixedly installed screw mand...

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PUM

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Abstract

The utility model relates to the field of inspection of pressure vessels for nuclear reactors in a nuclear power station, and particularly discloses an automatic shifting platform for welding inspection of an adapter of a pressure vessel. The automatic shifting platform comprises an inner core tube and an outer sleeve, wherein a screw rod is fixedly arranged in the inner core tube; a linear guide rail is arranged on the outer wall of the inner core tube; a slotted channel is arranged on the inner wall of the outer sleeve; a screw rod sleeve is fixedly arranged in the outer sleeve; a guide rail support is arranged on the inner wall of the upper end of the outer sleeve; a nut is arranged at the upper end of the screw rod sleeve; threads are processed on the outer wall of the screw rod; and the upper end of the screw rod is connected with a worm gear drive device and a motor. The motor drives the worm gear drive device to rotate to further drive the screw rod to drive, so as to enable matched transmission of the screw rod and the screw rod sleeve, so that the platform can be lifted and lowered, and the horizontal heights of corresponding maintenance devices connected to the lower part of the automatic shifting platform are stable and controllable; meanwhile, by virtue of the cooperation of the linear guide rail and the guide rail support, and lifting and lowering of the platform can be limited to achieve stable running, so as to guarantee safety of the automatic shifting platform in a reactor.

Description

technical field [0001] The invention belongs to the field of inspection of nuclear reactor pressure vessels of nuclear power plants, and in particular relates to an automatic displacement platform for inspection of weld seams of connection pipes of pressure vessels. Background technique [0002] Reactor pressure vessel (reactor pressure vessel) is a closed container that houses a nuclear reactor and withstands its huge operating pressure. It is also called a reactor pressure vessel. It is a key equipment in a pressurized water reactor nuclear power plant. Moreover, it is non-replaceable equipment, which must be absolutely safe and reliable during the 60-year life of the nuclear power plant. Since the cooling medium (water) in the nuclear primary circuit is highly radioactive and highly polluting after the operation of the nuclear power plant, auxiliary tools are required to carry out these inspections, and the inspections need to be remote and automated. [0003] A general ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/003G21C17/01
CPCY02E30/30
Inventor 王俊涛周亮聂勇刘小林张志义何秀权
Owner RES INST OF NUCLEAR POWER OPERATION