WO2016068461A1 - Instrument placé dans le cœur d'un réacteur, à durabilité améliorée - Google Patents

Instrument placé dans le cœur d'un réacteur, à durabilité améliorée Download PDF

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Publication number
WO2016068461A1
WO2016068461A1 PCT/KR2015/008467 KR2015008467W WO2016068461A1 WO 2016068461 A1 WO2016068461 A1 WO 2016068461A1 KR 2015008467 W KR2015008467 W KR 2015008467W WO 2016068461 A1 WO2016068461 A1 WO 2016068461A1
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WO
WIPO (PCT)
Prior art keywords
emitter
instrument
present
insertion hole
signal line
Prior art date
Application number
PCT/KR2015/008467
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English (en)
Korean (ko)
Inventor
차균호
노경호
김용덕
문상래
배성만
Original Assignee
한국수력원자력 주식회사
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Publication date
Application filed by 한국수력원자력 주식회사 filed Critical 한국수력원자력 주식회사
Publication of WO2016068461A1 publication Critical patent/WO2016068461A1/fr

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/108—Measuring reactor flux
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00—Measuring neutron radiation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/08—Structural combination of reactor core or moderator structure with viewing means, e.g. with television camera, periscope, window
    • 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 an in-vehicle instrument with improved durability, and more particularly to an in-vehicle instrument for measuring the output distribution of the core is important in the safe operation of nuclear power plants.
  • the most important indicator for the safe operation of a reactor is the output peak factor, and to monitor this value, it must be possible to continuously measure the correct three-dimensional output distribution of the core.
  • the output distribution of the core is measured by the internal instrument. There are two types of the internal instrument of the nuclear power plant.
  • Mobile furnace instrument which mainly uses a fission chamber, can be used for the lifetime of the nuclear power plant, and it has the advantage of measuring accurate 3D core output distribution, but the output distribution measurement is performed only periodically. line) There is a disadvantage that cannot be measured.
  • the fixed internal measuring instrument has the advantage that the on-line measurement is possible, but there is a disadvantage that the meter must be replaced periodically because the emitter material generating the core output signal reacts with the neutrons in the core and burns.
  • the stationary furnace instrument may be classified into a bottom mounted ICI loaded at the bottom of the core and a top-mounted ICI loaded at the top of the core.
  • FIG. 1 is a view schematically illustrating a reactor to which a bottom mounted furnace instrument is applied
  • FIG. 2 is a view schematically illustrating a reactor to which a bottom mounted furnace instrument is applied.
  • the furnace instrument 10 is loaded-drawn-reloaded into the reactor 1 through a curved path.
  • the furnace instrument 10 must undergo a load-draw-reload several times through a path of greater bending than the bottom mounted type.
  • the new neutron probe 10 which has not been neutron probed, is initially stored in the core outside the core for nuclear fuel replacement after the neutron probe is received at the core for approximately 18 months of operation.
  • the in-vehicle instrument 10 which has been subjected to neutron irradiation to start the next cycle operation, is reloaded to its original position and subjected to neutron irradiation again. That is, due to the repeated loading and reloading of rhodium 2-4 times and vanadium / cobalt / platinum 5-7 times, the material of the internal measuring instrument 10 is accompanied by changes in materials such as deformation and material embrittlement by neutron irradiation. Ultimately, short circuits occur at the emitter and signal line connections.
  • the fixed furnace instrument has a form of a so-called self-powered neutron detector (SPND) that does not require an external power source, in which the atomic nucleus of the inner conductor and the proton react to generate electrons to generate a current proportional to the output. .
  • SPND self-powered neutron detector
  • FIG. 3 is a conceptual diagram briefly illustrating a configuration of a conventional spontaneous neutron measuring instrument.
  • the spontaneous neutron measuring instrument 10 includes an emitter 11, which is an internal conductor that emits electrons, an insulator 12 that withstands radiation, and insulates internal and external conductors, and collects current by collecting electrons. It consists of an outer conductor (collector, or sheath) 13 and a lead wire 14 to generate a.
  • the emitter 11 and the signal line 14 are joined by welding.
  • the emitter 11 is a material that emits electrons by reacting with a neutron, and may mainly consist of a noble metal or a general metal.
  • the signal line 14 may be made of Inconel 600, which is mainly a nickel-based alloy, as a material having a small reaction with neutrons. That is, the emitter 11 and the signal line 14 are a combination of a single metal (noble metal or a general metal) and an alloy, and the coupling is performed by welding between dissimilar metals.
  • braze welding has a weak shear stress, which causes fracture at the high temperature and radiation effect, and also develops surface defects during long-term use due to brittleness of the signal line, resulting in lateral stress. ) Is weighted. As a result, due to this phenomenon, there is a problem in that a signal connection line is shorted due to the problem of the welding part in the course of traveling between the core environment of 350 ° C. or higher and the core external environment of room temperature several times.
  • An object of the present invention is to provide an in-vehicle instrument having improved durability which allows the durability of an in-vehicle instrument to be loaded-drawn-reloaded into the reactor.
  • the furnace instrument having improved durability includes an emitter for emitting electrons, an insulator for isolating a conductor, an external conductor for collecting current and generating current by collecting the electrons, and a signal line connected to the emitter, An insertion hole is formed at the center and the signal line may be inserted into the insertion hole and fastened to the emitter.
  • the emitter has a diameter of 0.5mm and a length of 400mm, the insertion hole may further include being processed to an inner diameter of 0.1mm.
  • the furnace measuring instrument having improved durability according to the present invention connects the emitter and the signal line by inserting the signal line into the insertion hole formed in the emitter of the furnace measuring instrument which reacts with the neutron, thereby connecting the emitter and the signal line. There is an effect of eliminating the defects of the internal measuring instrument.
  • the furnace instrument improved durability according to the present invention can calculate the accurate output distribution of the core, there is an effect that can reduce the purchase cost of the furnace instrument due to the reduction rate of the furnace instrument failure.
  • the durability of the furnace instrument according to the present invention can significantly reduce the amount of waste in the furnace instrument after use as a high-level radioactive material by reducing the number of discarded furnace instrument, which can secure a high-level waste space as well as nuclear power plants It can also contribute to reducing workers' exposure.
  • FIG. 1 is a schematic view of a reactor to which a bottom mounted furnace instrument is applied.
  • FIG. 2 is a view schematically illustrating a reactor to which a bottom mounted furnace instrument is applied.
  • FIG. 3 is a conceptual diagram briefly illustrating a configuration of a conventional spontaneous neutron measuring instrument.
  • FIG. 4 is a conceptual diagram briefly illustrating a configuration of a spontaneous neutron measuring instrument according to the present embodiment.
  • FIG. 4 is a conceptual diagram briefly showing the configuration of a spontaneous neutron measuring instrument according to the present embodiment.
  • the spontaneous neutron meter 100 has a difference in the coupling relationship between the emitter 110 and the signal line 140, the rest of the configuration is to be similar to the conventional spontaneous neutron meter Can be.
  • the spontaneous neutron meter 100 may include an emitter 110, an insulator 120, an external conductor 130, and a signal line 140.
  • the emitter 110 is disposed inside the outer conductor 130, and the insulator 120 is filled between the emitter 110 and the outer conductor 130.
  • the spontaneous neutron measuring instrument 100 is formed with an insertion hole 111 inside the emitter 110.
  • the signal line 140 may be inserted into the insertion hole 111 to be fastened to the emitter 110.
  • the emitter 110 may have a diameter of 0.5 mm and a length of 400 mm, and the insertion hole 111 may have an inner diameter of 0.1 mm.
  • the signal line 140 is inserted into the insertion hole 111 formed in the emitter 110 without braze welding the emitter 110 and the signal line 140.
  • the rotor 110 and the signal line 140 are fastened.
  • the spontaneous neutron measuring instrument 100 not only the emitter 110 and the signal line 140 can maintain a firm connection state, but also the contact area between the emitter 110 and the signal line 140 is enlarged. The defect of the signal generated from the emitter 110 may be reduced.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Molecular Biology (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Measurement Of Radiation (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

L'invention concerne un instrument placé dans le cœur d'un réacteur, présentant une durabilité améliorée, cet instrument étant chargé dans, retiré de, et chargé à nouveau dans l'intérieur d'un réacteur nucléaire, et comprenant : un émetteur pour émettre des électrons ; un isolateur pour isoler un collecteur ; un collecteur extérieur pour générer du courant par agrégation des électrons ; ainsi qu'un fil conducteur connecté à l'émetteur, cet émetteur étant pourvu d'un trou d'insertion dans son centre et un fil conducteur étant inséré dans le trou d'insertion pour être couplé à l'émetteur ; ainsi, l'invention résout la défaillance de l'instrument placé dans le cœur d'un réacteur, provoquée par le court-circuitage du fil conducteur.
PCT/KR2015/008467 2014-10-30 2015-08-13 Instrument placé dans le cœur d'un réacteur, à durabilité améliorée WO2016068461A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
KR10-2014-0149606 2014-10-30
KR1020140149606A KR20160051987A (ko) 2014-10-30 2014-10-30 내구성이 향상된 노내계측기

Publications (1)

Publication Number Publication Date
WO2016068461A1 true WO2016068461A1 (fr) 2016-05-06

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KR (1) KR20160051987A (fr)
WO (1) WO2016068461A1 (fr)

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0646393U (ja) * 1992-11-21 1994-06-24 助川電気工業株式会社 自己出力形中性子検出器
KR100301297B1 (ko) * 1992-06-22 2001-10-22 드폴 루이스 에이 노심내고정형검출기및원자로내의출력분포결정방법
KR20080011782A (ko) * 2006-07-31 2008-02-11 한국전력공사 하이브리드형 노내 계측기 조립체 및 계측 방법
KR20100004572U (ko) * 2008-10-27 2010-05-07 한국전력공사 장수명 실시간 국부과출력보호용 노내 계측기 조립체
KR100960228B1 (ko) * 2009-12-30 2010-06-01 주식회사 우진 고정형 노내핵계측기

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100301297B1 (ko) * 1992-06-22 2001-10-22 드폴 루이스 에이 노심내고정형검출기및원자로내의출력분포결정방법
JPH0646393U (ja) * 1992-11-21 1994-06-24 助川電気工業株式会社 自己出力形中性子検出器
KR20080011782A (ko) * 2006-07-31 2008-02-11 한국전력공사 하이브리드형 노내 계측기 조립체 및 계측 방법
KR20100004572U (ko) * 2008-10-27 2010-05-07 한국전력공사 장수명 실시간 국부과출력보호용 노내 계측기 조립체
KR100960228B1 (ko) * 2009-12-30 2010-06-01 주식회사 우진 고정형 노내핵계측기

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KR20160051987A (ko) 2016-05-12

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