Thermal test device and centering method for control rod driving wire

A thermal test and driving line technology, applied to pump devices, educational appliances, machines/engines, etc., can solve the problems of not specifying, adjusting the centering of the test piece, and unsatisfactory, so as to achieve simple structure and ensure straight line degree, the effect of increasing reliability

Active Publication Date: 2021-10-29
CHINA NUCLEAR POWER TECH RES INST CO LTD +3
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, this scheme also cannot meet the requirements of operation under high temperature (≥300°C) and high pressure (≥15MPa); and there is no specific technical scheme on how to adjust the centering degree of the test piece

Method used

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  • Thermal test device and centering method for control rod driving wire
  • Thermal test device and centering method for control rod driving wire
  • Thermal test device and centering method for control rod driving wire

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Embodiment Construction

[0032]In order to describe the content, structural features, achieved goals and effects of the present invention in detail, the following will be described in detail in combination with the embodiments and accompanying drawings.

[0033] see Figures 1 to 3 , the invention discloses a thermal test device for control rod drive line, comprising a bottom connection shell 1, a lower pressure shell 2, a middle pressure shell 3, an upper pressure shell 4, a lower core plate 5, a surrounding Plate assembly 6, upper core plate 7, guide tube support plate 8, guide tube 9, tube seat installation structure 10 and tube seat 0 for installing control rod drive mechanism. The bottom connection shell 1, the lower pressure shell 2, the middle pressure shell 3 and the upper pressure shell 4 are sequentially sealed and connected, and the two ends of the lower pressure shell 2 are respectively formed with a lower plate installation notch 21 and an upper plate installation notch 22 , the lower co...

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Abstract

The invention discloses a thermal test device for a control rod drive line and a centering method thereof, wherein the thermal test device for a control rod drive line includes a bottom connection shell, a lower pressure shell, a middle pressure shell, an upper The pressure shell, the lower core plate, the coaming assembly, the upper core plate, the guide cylinder support plate, the guide cylinder, the pipe seat installation structure and the pipe seat, and the two ends of the upper and lower flanges of the lower pressure shell are respectively formed with upper plate mounting plates. The lower core plate is fixed on the lower plate installation notch, the coaming assembly is located in the lower pressure shell and fixed on the lower core plate, and the coaming assembly is provided with multiple The upper core plate is fixed on the installation notch of the upper plate, and the upper core plate is provided with a plurality of upper plate adjustment members along its circumference, and the upper end flange of the middle pressure shell is formed with a support plate installation notch, guiding The cylinder support plate is fixed on the installation notch of the support plate, and the guide cylinder support plate is provided with a plurality of support plate adjustment parts along its circumference.

Description

technical field [0001] The invention relates to the technical field of reactor test verification, in particular to a thermal test device for a control rod driving line and a centering method thereof. Background technique [0002] The Chinese patent with the patent number ZL201310454835.X discloses a cold-state test device and test method for the control rod drive line of a nuclear power plant. Components and driving mechanism; the pressure-bearing cylinder is a container composed of a top cylinder, an upper cylinder, a lower cylinder and a bottom connecting cylinder, and each section of the cylinder is detachably connected by flanges in turn; the test method is through By replacing one or more sections of the top cylinder, upper cylinder, and lower cylinder, the axial dimension of the pressure-bearing cylinder can be lengthened or shortened, so that the core fuel assemblies with different active section heights can be cooled test. However, in practice, the control rod driv...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G09B23/20
CPCG09B23/20Y02E30/30G21C17/017G21C13/036G21C7/12
Inventor 苏前华卢冬华张戈吕路路付学宽柳红超李瑜
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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