Main shaft translation winding mechanism for dismounting nuclear reactor detector assembly and using method

A technology for detector components and nuclear reactors, which is applied in the direction of nuclear reactor monitoring, reactor fuel elements, reactors, etc., and can solve the problems of patent application for the main shaft translation and winding technology without detector components.

Active Publication Date: 2021-01-08
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] So far, there is no patent application for the spindle translation winding technology during the dismantling of the detector assembly at home and abroad.

Method used

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  • Main shaft translation winding mechanism for dismounting nuclear reactor detector assembly and using method
  • Main shaft translation winding mechanism for dismounting nuclear reactor detector assembly and using method
  • Main shaft translation winding mechanism for dismounting nuclear reactor detector assembly and using method

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0094] Such as figure 1 , figure 2 as shown,

[0095] Such as figure 1 , figure 2 Schematic side view of the shielding structure for removal of the nuclear reactor detector assembly.

[0096] figure 1 with figure 2 The shield structure shown is image 3 The shielding structure 304 in.

[0097] The subsequent front and back refer to the direction facing the legend paper and the direction facing away from the paper as shown in the figure.

[0098] shielding structure, including:

[0099] The left shield body 3048A, the right shield body 3048B, the left shield shaft 3049A, and the right shield shaft 3049B; the left shield body 3048A is rotatably connected around the left shield shaft 3049A, and the right shield body 3048B is rotatably connected around the right shield shaft 3049B; the left shield body Shaft 3049A and right shielding shaft 3049B are at the same level. The distance between left shielding shaft 3049A and right shielding shaft 3049B needs to ensure that l...

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PUM

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Abstract

The invention discloses a main shaft translation winding mechanism for dismounting a nuclear reactor detector assembly and a use method. The main shaft translation winding mechanism comprises an opening and closing slide rail (315) arranged in an outer frame body (307), and a left winding main shaft module (302) and a right winding main shaft module (305) which are assembled along the opening andclosing sliding rail (315) in a sliding manner, also comprises an integral translation sliding rail (303) which is arranged in the outer frame body (307), and an integral translation frame (314) whichis assembled along the integral translation sliding rail (303) in a sliding manner; the left winding main shaft module (302) and the right winding main shaft module (305) are simultaneously assembledwith the integral translation frame (314) in a linkage manner; the main shaft translation winding mechanism comprises an integral translation driving assembly (301) which is connected to the integraltranslation frame (314) and is used for controlling an integral translation driving assembly to translate along the integral translation sliding rail (303); and the main shaft translation winding mechanism comprises an opening and closing driving assembly which is connected to the left winding main shaft module (302) and the right winding main shaft module (305) and controls the left winding mainshaft module (302) and the right winding main shaft module (305) to move along the opening and closing sliding rail (315) in the same direction or opposite directions.

Description

technical field [0001] The invention relates to the technical field of dismantling of reactor equipment, in particular to a main shaft translational winding mechanism for dismantling a detector assembly of a nuclear reactor and a use method thereof. Background technique [0002] The Hualong No. 1 nuclear reactor adopts an advanced core measurement system. Compared with the M310 type power station, the opening of the bottom head of the pressure vessel is cancelled, which improves safety. The neutron-temperature detector assembly introduced from the top cover of the reactor pressure vessel in the advanced core measurement system is affected by the burnup, and the overall replacement of the detector assembly needs to be considered after 2 to 3 refueling cycles. Although the AP1000 power station uses similar detector components and needs to be replaced regularly, no relevant replacement equipment has been found. Before the present invention, the Russian VVER-1000 stack type (th...

Claims

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Application Information

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IPC IPC(8): G21C19/02G21C17/00
CPCG21C19/02G21C17/00Y02E30/30
Inventor 湛卉杨其辉安彦波熊思勇瓮松峰朱松伟李娜余志伟黄辉张翼刘昌文王炳炎王尚武任荷李燕
Owner NUCLEAR POWER INSTITUTE OF CHINA
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