Apparatus and method for automatically and remotely measuring the internal gap of a reactor

A technology for nuclear reactors and gaps, which is applied to measurement devices, reactors, nuclear reactor monitoring, etc., can solve the problems of increased measurement and construction periods, long time consumption, and difficulty in obtaining measurement values, so as to improve work efficiency and shorten construction periods. Effect

Active Publication Date: 2011-04-13
KOREA HYDRO & NUCLEAR POWER CO LTD
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0034] In the traditional process of measuring the gap 9, since it takes a long time to manually measure 72 points of the gap in a small space, the measurement cycle and construction cycle increase accordingly
[0035] In addition, in the traditional process of measuring the gap 9, it is difficult to obtain objective measurement values ​​because the measurer has to measure 72 points in a very narrow space

Method used

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  • Apparatus and method for automatically and remotely measuring the internal gap of a reactor
  • Apparatus and method for automatically and remotely measuring the internal gap of a reactor
  • Apparatus and method for automatically and remotely measuring the internal gap of a reactor

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Embodiment Construction

[0048] Hereinafter, preferred embodiments of the remote and precise gap measuring device according to the present invention will be described in detail with reference to the accompanying drawings.

[0049] Figure 4 is a schematic diagram showing said remote, precise gap measurement device according to the present invention, Figure 5 is an assembly drawing showing the gauge block and sensor.

[0050] Such as Figure 4 As shown, the remote, precise gap measurement device includes: a plurality of digital probes 14 for measuring distances, data processing components, air components and power supply components for manipulating the digital probes.

[0051] 4 to 6 digital detectors 14 can be inserted into the core support cylinder protrusion 7 .

[0052] In order to reduce time and cost to effectively measure the gap, it is preferable to insert at least 4 digital detectors 14 into the core support cylinder protrusion 7 .

[0053] Thus, 16 to 24 digital detectors 14 can be conne...

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PUM

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Abstract

The present invention relates to a remote, precise gap-measuring apparatus for automatically measuring the gap between reactor internals comprising a nuclear reactor vessel, a core support barrel, a core shroud and a lower support structure, the remote, precise gap-measuring apparatus comprising one and more digital probes measuring a gap between a nuclear reactor vessel protrusion and a core support barrel protrusion, the nuclear reactor vessel protrusions being disposed on an inner surface of the nuclear reactor vessel, the core support barrel protrusions being disposed on an outer surface of the core support barrel and engaged with the nuclear reactor vessel protrusions; a computer coupled to the digital probes to display and store a measured value of the gap measured by the digital probes; and a solenoid valve controlled by the computer, the solenoid valve controlling compressed air supplied through an air hose to operate the digital probe, wherein the digital probes measure the gap after the core support barrel, the core shroud and the lower support structure are welded to each other, thereby decreasing the construction period and simplifying the construction process.

Description

technical field [0001] The present invention relates to a remote and accurate gap measuring device for automatically measuring the gap between reactor internal components, and more particularly to such a remote and precise gap measuring device which can be used during the construction of a nuclear power plant when When the core support cylinder, core shroud and lower support structure are assembled and installed in the nuclear reactor vessel, the gap is automatically measured so that the gap between the nuclear reactor vessel protrusion and the core support cylinder protrusion meets the allowable clearance requirements . Background technique [0002] figure 1 A transverse cross-sectional view showing the internals of a conventional reactor. figure 2 A longitudinal section showing conventional reactor internals. image 3 It is a partial cross-sectional view, showing the gap 9 between the core support tube protrusion 7 and the nuclear reactor vessel protrusion 8 in a conve...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/10G21C17/08
CPCG21C13/02G01B7/14G21C17/10G21C19/207Y02E30/30
Inventor 李载坤姜龙澈高涂英申在泽
Owner KOREA HYDRO & NUCLEAR POWER CO LTD
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