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Reactor internal hoisting tool

A technology for hoisting tools and internal components, applied in the direction of reactor fuel elements, reactors, nuclear engineering, etc., to achieve the effect of firm grasping and release

Active Publication Date: 2013-12-25
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, the above-mentioned slings for pressurized water reactors cannot achieve this function, so it is necessary to develop a lifting tool for reactor internals suitable for small modular reactors

Method used

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Examples

Experimental program
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Effect test

Embodiment Construction

[0021] Such as figure 1 , figure 2 As shown, the reactor internals lifting tool of the present invention includes a lifting ring 1, an operating rod 2, a movable support guide rod 3, a movable support guide cylinder 4, a core measurement assembly grabber 5, a reactor internals lifting head 6 and a movable support 8. The suspension ring 1 is respectively connected to the connecting flanges on the wall of the movable support guide cylinder 4 in three vertical directions through three connecting rods evenly distributed at its lower end, and each movable support guide cylinder 4 has a hollow The movable support guide rod 3 passes through, and the upper end of the movable support guide rod 3 is positioned at the outside of the movable support guide cylinder 4; The outer sleeve of the root operating rod 2 is connected, and the inner core rod of the operating rod 2 passes through the movable support guide rod 3 and is connected with the petal-shaped stack internal component hoistin...

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PUM

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Abstract

The invention belongs to nuclear reactor internal hoisting equipment and particularly relates to a reactor internal hoisting tool. A lifting ring is respectively connected with connecting flanges through three connecting rods which are evenly disposed on the lower end of the lifting ring, and the connecting flanges are disposed on cylinder walls of three movable support guide cylinders in the vertical direction. Each movable support guide cylinder is provided with a hollow movable support guide rod which penetrates through the movable support guide cylinder. The upper end of each movable support guide rod is located outside the movable support guide cylinder. Each operating rod is composed of an external sleeve and an internal core bar. The upper end portion of each movable support guide rod is connected with the external sleeve of one operating rod. The internal core bar of each operating bar penetrates through the movable support guide rod and is connected with one petaling reactor internal hoisting head. Movable supports are respectively disposed on three movable support guide cylinders. Six sets of measuring assembly gripping apparatus are installed on the lower portions of the movable supports. The reactor internal hoisting tool controls the measuring assembly gripping apparatus to grab or release measuring assemblies through air cylinders, and controls the reactor internal hoisting heads to grab or release reactor internals through the operating rods.

Description

technical field [0001] The invention belongs to nuclear reactor internal component hoisting equipment, in particular to a reactor internal component hoisting tool. Background technique [0002] The reactor upper internals are important structural parts in the core. During the installation and refueling maintenance of the new reactor, it needs to be installed and disassembled. Due to the operation in a strong radiation environment, and the installation accuracy is high, the operation interface For special reasons, it is necessary to use special hoisting equipment for upper reactor internals. The equipment is a specially designed spreader with a structure suitable for a specific reactor, and can be accurately connected with the upper reactor internals for installation, disassembly, lifting and other operations. [0003] At present, the spreader for the upper reactor internals used in the refueling overhaul of the pressurized water reactor in service consists of a suspender, a...

Claims

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Application Information

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IPC IPC(8): G21C19/02G21C19/20
CPCY02E30/30
Inventor 王炳炎谭文界黄新东戴旭东任荷安彦波谭宏伟
Owner NUCLEAR POWER INSTITUTE OF CHINA
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