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A driving line misalignment test device and test method

A test device and driving line technology, applied in the field of nuclear reactors, can solve the problems of conservative test data and achieve the effect of rich and complete test data

Active Publication Date: 2022-04-29
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0003] And any type of drive line equipment must pass the misalignment friction test. The existing drive line misalignment friction test has only one misalignment amount, so the obtained test data is relatively conservative.

Method used

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  • A driving line misalignment test device and test method

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Embodiment

[0028] A drive line misalignment test device, including a loop flange 1, the loop flange 1 is used to connect the drive line 2 and the pressure vessel 3, and the center line 6 of the drive line is connected to the stack in the pressure vessel 3 The component centerline 7 is misaligned.

[0029] Specifically, the looper flange 1 is concentrically set on the top of the pressure vessel 3, so that the centerline of the looper flange 1 is the rotation centerline 5, and the gap between the looper flange 1 and the pressure vessel 3 passes through O Type sealing ring seal 8, and the design pressure is 3MPa.

[0030] The driving line 2 is fixedly connected to the loose flange 2 through the fixed flange 4, so as to accurately control the misalignment of the driving line 2 and the loose flange 1.

[0031] In this embodiment, the driving wire 2 is welded in the flange hole of the fixing flange 4, so as to ensure that the driving wire 2 is relatively fixed to the fixing flange 4 and the d...

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PUM

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Abstract

The present invention relates to the technical field of nuclear reactors, in particular to a drive line misalignment test device, the adopted technical solution is: a drive line misalignment test test device, the drive line and the pressure vessel pass through a loose flange connected, and the centerline of the driving line is misaligned with the centerline of the internal components in the pressure vessel. The misalignment test can be carried out according to the initial misalignment amount during assembly and connection to obtain the test data under a single misalignment amount; then the looper flange can be rotated to change the centerline of the drive line and the reactor internals in the pressure vessel The misalignment amount of the center line, and then obtain the misalignment test data of the driving line under different misalignment amounts. Therefore, under the set pressure, the present invention can realize the adjustment of the misalignment amount from zero to twice the maximum deviation between the centerline of the drive line and the center line of the internal components, so as to obtain more test data and provide a basis for the accuracy of the drive line. Control provides data support.

Description

technical field [0001] The invention relates to the technical field of nuclear reactors, in particular to a driving line misalignment testing device and testing method. Background technique [0002] The driving line (control rod driving rod) belongs to the core equipment of the nuclear reactor, and plays a key role in controlling the reactivity in the case of changing the power of the nuclear reactor and emergency shutdown. When the drive wire lifts or releases the control rod, the movement speed of the control rod directly determines its sensitivity to nuclear reactivity control, and the frictional resistance caused by the misalignment between the drive wire and the internal components reduces the sensitivity most important factor. [0003] And any type of drive line equipment must pass the misalignment friction test. The existing drive line misalignment friction test has only one misalignment amount, so the obtained test data is relatively conservative. The actual median...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01B21/24G01M13/00G01M7/08G21C17/00
CPCG01B21/24G01M13/00G01M7/08G21C17/00Y02E30/30
Inventor 肖林海王运生马新光史天蛟钟宇航聂常华吴小飞田雪莲
Owner NUCLEAR POWER INSTITUTE OF CHINA