WO2015072710A1 - Système et procédé de contrôle du nombre de tuyau de transfert thermique de générateur de vapeur dans une centrale nucléaire - Google Patents

Système et procédé de contrôle du nombre de tuyau de transfert thermique de générateur de vapeur dans une centrale nucléaire Download PDF

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Publication number
WO2015072710A1
WO2015072710A1 PCT/KR2014/010743 KR2014010743W WO2015072710A1 WO 2015072710 A1 WO2015072710 A1 WO 2015072710A1 KR 2014010743 W KR2014010743 W KR 2014010743W WO 2015072710 A1 WO2015072710 A1 WO 2015072710A1
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WO
WIPO (PCT)
Prior art keywords
heat pipe
steam generator
image
camera
hole
Prior art date
Application number
PCT/KR2014/010743
Other languages
English (en)
Korean (ko)
Inventor
신호철
정경민
서용칠
Original Assignee
한국원자력연구원
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 한국원자력연구원 filed Critical 한국원자력연구원
Priority to CN201480061436.XA priority Critical patent/CN105706178B/zh
Publication of WO2015072710A1 publication Critical patent/WO2015072710A1/fr

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G21C19/207—Assembling, maintenance or repair of reactor components
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/006—Details of nuclear power plant primary side of steam generators
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a system and method for identifying a heat pipe number of a steam generator in a nuclear power plant, and more particularly, to a system and method for checking a heat pipe number of a steam generator using a camera.
  • nuclear power plants are usually divided into a nuclear steam supply system centered on a nuclear reactor, a generator system such as a turbine that supplies steam to run a generator, and other auxiliary equipment.
  • the nuclear steam supply system is also referred to as the primary system
  • the generator system is also referred to as the secondary system.
  • the reactor is a device made to be used for various purposes such as generating heat by artificially controlling the chain fission reaction of fissile material, the production of radioisotopes and plutonium, or the formation of a radiation field, the core configuration of the primary system Element.
  • the steam generated through the nuclear steam supply system 10 composed of a pressurizer 11, steam generator 13, the main coolant pump 15 turbine 21 and the generator ( 23) is made to obtain electrical energy through the generator system 20 included.
  • the steam generator 13 is to convert the low temperature water of the liquid state into high temperature and high pressure steam by using the heat generated during nuclear fission in the reactor 17, by the force of the steam converted in the steam generator 13
  • the turbine 21 and the generator 23 are rotated to generate power.
  • the steam generator 13 is a device composed of a plurality of tubes, the inside is called a heat transfer tube, the sludge may accumulate or deform therein depending on the number of years of operation, and damage such as small cracks may occur. Therefore, it is recommended to inspect the heat pipes of the steam generator 13 periodically during the preventive maintenance of nuclear fuel cell protection.
  • Korean Patent No. 10-1160660 discloses a technique for introducing a heat pipe inspection robot into a steam generator.
  • the heat pipe inspection robot checks the number of columns and rows indicated on the tube sheet without the heat pipe, and then counts the number of heat pipes to be inspected. Since only the number of the heat pipes is checked, there is a problem that it is very troublesome and the possibility of human error is very high.
  • the heat pipe number identification system of the nuclear steam generator according to an embodiment of the present invention and the heat pipe number identification method of the nuclear steam generator according to another embodiment are aimed at the following problems in order to solve the above problems.
  • Nuclear steam generator heat pipe number identification system is disposed inside the nuclear power plant steam generator 100 chamber, the camera 110 and the camera to shoot the tube sheet 120 located on the top of the steam generator ( And an image device for generating the heat transfer tube position number 230 on the image 210 of the heat transfer tube hole formed in the tube sheet after receiving the acquired image and outputting the image to the screen 200.
  • Nuclear steam generator heat pipe number identification method is the first step in which the camera 110 disposed inside the nuclear power plant steam generator 100 photographs the tube sheet 120 located on the steam generator chamber top (S100); And
  • Nuclear steam generator heat pipe number identification system according to an embodiment of the present invention and nuclear steam generator heat pipe number identification method according to another embodiment by using a pan / tilt / zoom camera and image processing technology together with the number of the heat pipe on the monitor screen Have it displayed.
  • 1 is a view showing the structure of a general nuclear power generation.
  • FIG. 2 is a view showing a nuclear steam generator heat pipe number identification system according to an embodiment of the present invention.
  • FIG 3 is a view showing a tube sheet in the nuclear steam generator heat pipe number identification system according to an embodiment of the present invention.
  • FIG. 4 is a view showing a tube sheet output on the screen of the imaging apparatus without image processing in the heat pipe number identification system of the nuclear steam generator according to an embodiment of the present invention.
  • FIG. 5 is a view showing a tube sheet output on the screen of the image device after the image processing in the heat pipe number identification system of the nuclear steam generator according to an embodiment of the present invention.
  • FIG. 6 is a flowchart illustrating a time series of a method for identifying a heat pipe number of a nuclear steam generator according to another embodiment of the present invention.
  • FIG. 2 is a view showing a heat pipe number identification system of the nuclear steam generator according to an embodiment of the present invention.
  • the heat pipe number identification system of the nuclear steam generator according to an embodiment of the present invention includes a camera 110 and the image device.
  • the camera 110 is disposed in the steam generator 100 of the nuclear power plant, and performs a function of photographing the tube sheet 120 located on the upper chamber of the steam generator 100.
  • the camera 110 may be a camera having a Charge Coupled Device (CCD) or a Complementary Metal-Oxide Semiconductor (CMOS) sensor, and the camera 110 may be a camera that generates less noise even in a low light environment.
  • CCD Charge Coupled Device
  • CMOS Complementary Metal-Oxide Semiconductor
  • the camera 110 preferably includes at least one of a zoom function, a panning function, and a tilting function.
  • the imaging apparatus performs a function of generating a heat pipe position number 230 on the image 210 of the heat pipe tube hole formed in the tube sheet 120 after receiving the image acquired by the camera 110 and outputting it to the screen.
  • FIG 3 is a view showing a tube sheet in the nuclear steam generator heat pipe number identification system according to an embodiment of the present invention
  • Figure 4 is an image processing in the heat pipe number identification system of the nuclear steam generator according to an embodiment of the present invention. The figure shows the tube sheet output on the screen of the imaging device without.
  • FIG. 5 is a diagram illustrating a heat transfer sheet output on a screen of an imaging apparatus after image processing in a heat pipe number identification system of a nuclear steam generator according to an embodiment of the present invention.
  • the camera 110 in the nuclear steam generator heat pipe number identification system uses a zoom function, a panning function, and a tilting function, and the tube sheet 120 located on the upper chamber of the steam generator 100. You should be able to take a picture of).
  • the tube sheet 120 includes a plurality of heat pipe holes 121 and a positioning number 122 disposed at a portion where the heat pipe holes are not formed.
  • These positioning numbers 122 are arranged at regular intervals in the tube sheet 120, and the numbers of the rows and columns at the arranged positions are written.
  • an image 210 of a heat pipe tube having a dark circular shape and an image 220 of a positioning number are displayed on the screen 200 of the imaging apparatus.
  • the imaging apparatus in the nuclear power plant steam generator heat pipe number identification system is a heat pipe on an image 210 of a heat pipe hole based on a positioning number 122 included in a tube sheet 120.
  • a location number 230 is generated and output to the screen 200.
  • the position number 230 of the heat pipes may be displayed all on the image 210 of each heat pipe tube, it may be displayed at a frequency enough to check the heat pipe number without looking complicated.
  • the camera 110 in the nuclear power plant steam generator tube number identification system includes at least one of a zoom function, a panning function, and a tilting function.
  • the position number 230 of the heat exchanger tube displayed on the image 210 of the heat exchanger hole is displayed. If a) is fixed, there is a problem that the matching of the position number 230 of the heat exchanger tube and the heat exchanger tube is broken.
  • the heat pipe position number 230 overlapped with the image 210 of the heat pipe hole on the screen 100 is matched with the image 210 of the heat pipe hole so as to change in accordance with the change of the image 210 of the heat pipe hole. To be required.
  • a three-dimensional graphic technique is used to create a row / column number having a smaller size than a heat pipe hole at a target heat pipe position, and then calibrate the camera to allow the camera 110 to operate. If the position of the, and the camera 110 to match the pre-made heat pipe number to the tube sheet position displayed on the acquired image to be displayed on the image, as shown in Figure 5 can be output by overlapping the number on the image 210 of the heat pipe hole Will be.
  • the camera in the steam generator 100 based on at least one of the position of the heat exchanger hole where the imaging apparatus knows the position, that is, the position or the center coordinate of the previously confirmed heat transfer tube hole 121 ( By obtaining the position parameter of the 110 it is possible to obtain the position information of the camera (110).
  • the imaging apparatus is located in the steam generator 100 based on at least one of the position identification number 122 formed on the tube sheet 120 and the position or center coordinates of the neighboring heat pipe holes 121. It is also possible to obtain the position information of the camera 110 by obtaining the position parameter of the camera 110.
  • the imaging apparatus can obtain the positional parameters of the camera 110 in the steam generator 100 on the basis of the position coordinates 122 and the center coordinates of the neighboring heat pipe holes 121.
  • FIG. 6 is a flowchart illustrating a time series of a method for identifying a heat pipe number of a nuclear steam generator according to another embodiment of the present invention.
  • the method for identifying a heat pipe number of a nuclear steam generator is a tube in which a camera 110 disposed inside a nuclear power plant steam generator 100 is located at the top of the steam generator chamber.
  • the second step (S200) is to obtain the positional parameters of the camera in the steam generator 100 based on the positioning number 122 and the position of the neighboring heat pipe holes 121, the image device is disposed on the tube sheet 120 Step 2-1 (S210) to match the image 210 of the heat pipe hall and the heat pipe position number 230 based on the position parameter of the camera 110 and the second step (S220) and the image of the heat pipe hall 210 And a second step S230 of outputting an image on which the heat pipe position number 230 is formed.
  • the camera 110 preferably includes at least one of a zoom function, a panning function, and a tilting function. As described above, the camera 110 enlarges, reduces, or reduces the image of the heat exchanger hole by the zoom function, the panning function, or the tilting function.
  • the heat pipe position number 220 is preferably matched with the image 210 of the heat pipe holes so as to change in accordance with the change of the image 210 of the heat pipe holes.
  • the imaging apparatus acquires a position parameter of the camera 110 in the steam generator 100 based on at least one of a known position, that is, a position or a center coordinate of the pre-confirmed heat pipe hole 121. It is possible to match 210 with the heat pipe position number 230.
  • a position parameter of the camera 110 in the steam generator 100 based on at least one of the position or the center coordinates of the position identification number 122 and the neighboring heat pipe holes 121 included in the heat transfer sheet of the heat pipe holes. It may be possible to match the image 210 with the heat pipe position number 230.
  • the center coordinate of the heat exchanger hole 121 may be obtained by the center of gravity method based on a dark area of the image acquired by the camera, and also a method of obtaining the center coordinate through the circumferential length and diameter of the heat transfer hole. would also be possible.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Un système de contrôle du nombre de tuyau de transfert thermique de générateur de vapeur nucléaire, selon un mode de réalisation de la présente invention, comprend : une caméra qui est disposée à l'intérieur d'un générateur de vapeur d'une centrale nucléaire et photographie une feuille de tube positionnée au niveau d'une extrémité supérieure du générateur de vapeur ; et un dispositif d'imagerie destiné à recevoir une image capturée par la caméra et générer un nombre de position d'un tuyau de transfert thermique sur une image d'un trou de tuyau de transfert thermique formé dans la feuille de tube pour délivrer en sortie l'image sur un écran.
PCT/KR2014/010743 2013-11-12 2014-11-10 Système et procédé de contrôle du nombre de tuyau de transfert thermique de générateur de vapeur dans une centrale nucléaire WO2015072710A1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201480061436.XA CN105706178B (zh) 2013-11-12 2014-11-10 核电站蒸汽发生器的传热管号码确认系统及方法

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
KR10-2013-0136683 2013-11-12
KR20130136683A KR101502702B1 (ko) 2013-11-12 2013-11-12 원자력 발전소 증기발생기 전열관 번호 확인 시스템 및 방법

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WO2015072710A1 true WO2015072710A1 (fr) 2015-05-21

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KR (1) KR101502702B1 (fr)
CN (1) CN105706178B (fr)
WO (1) WO2015072710A1 (fr)

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH09257981A (ja) * 1996-03-18 1997-10-03 Hitachi Ltd 燃料集合体確認システム
KR100364185B1 (ko) * 1999-12-29 2002-12-11 한전기공주식회사 핵연료 코어 맵핑 폴
KR20100059346A (ko) * 2008-11-26 2010-06-04 한전케이피에스 주식회사 증기발생기 수실 내부의 원격 육안검사 시스템
JP2012047526A (ja) * 2010-08-25 2012-03-08 Chugoku Electric Power Co Inc:The 燃料集合体及び燃料番号確認方法
KR20130036412A (ko) * 2011-10-04 2013-04-12 대우조선해양 주식회사 열교환기의 튜브 맵 생성 시스템 및 위치측정 방법

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2686283B1 (fr) * 1992-01-21 1994-03-18 Cga Hbs Cie Gle Automatisme Procede et dispositif pour reperer la position d'un outil sur la plaque tubulaire d'un faisceau de tubes.
FR2697632B1 (fr) * 1992-11-03 1994-12-16 Electricite De France Système de repérage d'un tube dans une boîte à eau de générateur de vapeur et procédé de mise en Óoeuvre de ce système.
US6282461B1 (en) * 1998-07-15 2001-08-28 Westinghouse Electric Company Llc Independent tube position verification system
CN101162617B (zh) * 2006-10-13 2010-11-10 核动力运行研究所 核蒸汽发生器水室内表面电视自动检查装置

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH09257981A (ja) * 1996-03-18 1997-10-03 Hitachi Ltd 燃料集合体確認システム
KR100364185B1 (ko) * 1999-12-29 2002-12-11 한전기공주식회사 핵연료 코어 맵핑 폴
KR20100059346A (ko) * 2008-11-26 2010-06-04 한전케이피에스 주식회사 증기발생기 수실 내부의 원격 육안검사 시스템
JP2012047526A (ja) * 2010-08-25 2012-03-08 Chugoku Electric Power Co Inc:The 燃料集合体及び燃料番号確認方法
KR20130036412A (ko) * 2011-10-04 2013-04-12 대우조선해양 주식회사 열교환기의 튜브 맵 생성 시스템 및 위치측정 방법

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KR101502702B1 (ko) 2015-03-13
CN105706178A (zh) 2016-06-22
CN105706178B (zh) 2017-10-20

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