FI81698B - Foerfarande foer foerhindrande av oavsiktligt kritiskt tillstaond i en kaernbraensledriven elkraftgenererande enhet. - Google Patents

Foerfarande foer foerhindrande av oavsiktligt kritiskt tillstaond i en kaernbraensledriven elkraftgenererande enhet. Download PDF

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Publication number
FI81698B
FI81698B FI832876A FI832876A FI81698B FI 81698 B FI81698 B FI 81698B FI 832876 A FI832876 A FI 832876A FI 832876 A FI832876 A FI 832876A FI 81698 B FI81698 B FI 81698B
Authority
FI
Finland
Prior art keywords
reactor
average
signal
boron
flux count
Prior art date
Application number
FI832876A
Other languages
English (en)
Finnish (fi)
Other versions
FI832876A0 (fi
FI81698C (sv
FI832876A (fi
Inventor
Jr Charles Richard Tuley
Douglas Arthur Bauman
Michal Marceli Feilchenfeld
Lesley Greenberg
James Albert Neuner
Original Assignee
Westinghouse Electric Corp
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 Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of FI832876A0 publication Critical patent/FI832876A0/fi
Publication of FI832876A publication Critical patent/FI832876A/fi
Application granted granted Critical
Publication of FI81698B publication Critical patent/FI81698B/fi
Publication of FI81698C publication Critical patent/FI81698C/sv

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Measurement Of Radiation (AREA)
  • Measurement Of Levels Of Liquids Or Fluent Solid Materials (AREA)

Claims (3)

1. Förfarande för att detektera ett av förbiseende uppträ-dande närmande tili kriticitet i en elektrisk effekt genere-rande anläggning med en kärnreaktor, innefattande följande stegs alstring av en momentan neutronilödesräknesignal som är representativ för det momentana neutronilödet i reaktorn när reaktorn ligger vid en reaktivitetsnivä av omkring 10—* procent eller nedre reaktoreffekt, kännetecknat av att därunder alstras ur den momentana neutronilödesräkningen en första och en andra genomsnittlig flödesräknesignal representativ för den genomsnittliga neutronflödesräknesig-nalen under minst första och andra stegringstidsperioder, vilka är skilda ät i tiden av ett förutbestämt tidintervall, inkluderande repetitiv sampling av den momentana neutronflö-desräknesignalen under nämnda stegringstidsperioder och alstring av nämnda första och andra genomsnittsflödesräk-nesignaler som genomsnittet av de sampel som tagits under respektive intervall; och jämföras nämnda första och andra genomsnittsflödesräknesignaler och alstras en alarm när den andra av genomsnittsflödesräknesignaler överstiger den första genomsnittsflödesräknesignalen med minst en förvald multiplikationsfaktor.
2. Förfarande enligt patentkrav 1, kännetecknat av att det förutbestämda tidintervallet är en multipel av nämnda stegringsperiod och innefattande stegen att repetitivt och kontinuerligt alstra nämnda genomsnittsflödesräknesignaler, lagring av den sista av dessa signaler, vars antal är nämnda multipel och vai som nämnda andra genomsnittsflödesräknesignal av den sista sä alstrade signalen.
3. Förfarande enligt patentkrav 2, kännetecknat av att nämnda sista genomsnittsflödesräknesignal jämförs med var och en av de nämnda lagrade genomsnittsflödesräknesignalerna och alarmsignalen alstras när den sista genomsnittsflödesräknesignalen överskrider nägon av de nämnda lagrade ge- 25 81 698 nomsnittsflödesräknesignalerna med minst nämnda multiplika-tionsfaktor.
FI832876A 1982-08-11 1983-08-10 Förfarande för förhindrande av oavsiktligt kritiskt tillstånd i en kär nbränsledriven elkraftgenererande enhet FI81698C (sv)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US06/407,231 US4582672A (en) 1982-08-11 1982-08-11 Method and apparatus for preventing inadvertent criticality in a nuclear fueled electric powering generating unit
US40723182 1982-08-11

Publications (4)

Publication Number Publication Date
FI832876A0 FI832876A0 (fi) 1983-08-10
FI832876A FI832876A (fi) 1984-02-12
FI81698B true FI81698B (fi) 1990-07-31
FI81698C FI81698C (sv) 1990-11-12

Family

ID=23611187

Family Applications (1)

Application Number Title Priority Date Filing Date
FI832876A FI81698C (sv) 1982-08-11 1983-08-10 Förfarande för förhindrande av oavsiktligt kritiskt tillstånd i en kär nbränsledriven elkraftgenererande enhet

Country Status (10)

Country Link
US (1) US4582672A (sv)
EP (1) EP0101242B1 (sv)
JP (1) JPS5948694A (sv)
KR (1) KR910004191B1 (sv)
DE (1) DE3372555D1 (sv)
ES (1) ES524844A0 (sv)
FI (1) FI81698C (sv)
FR (1) FR2531802B1 (sv)
GB (1) GB2125200B (sv)
ZA (1) ZA835144B (sv)

Families Citing this family (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6115300A (ja) * 1984-06-29 1986-01-23 ホーチキ株式会社 火災警報装置
US4678622A (en) * 1985-08-20 1987-07-07 General Electric Company Transient monitor for nuclear reactor
US4671919A (en) * 1985-08-23 1987-06-09 Westinghouse Electric Corp. Reactor power level monitoring system using an alpha-beta tracker
US4804514A (en) * 1986-12-09 1989-02-14 Westinghouse Electric Corp. Method and apparatus for neutron dosimetry
US4783307A (en) * 1987-03-05 1988-11-08 Commonwealth Edison Company Reactor control system verification
US4920548A (en) * 1988-09-28 1990-04-24 Westinghouse Electric Corp. Source range neutron flux count rate system incorporating method and apparatus for eliminating noise from pulse signal
US5164895A (en) * 1990-03-16 1992-11-17 Westinghouse Electric Corp. Neutron flux mapping system for nuclear reactors
US5076998A (en) * 1990-06-21 1991-12-31 Westinghouse Electric Corp. Monitoring of low frequency pulse rate
US5555279A (en) * 1994-11-16 1996-09-10 Nir; Israel System for monitoring and controlling nuclear reactors
US6061412A (en) * 1995-10-05 2000-05-09 Westinghouse Electric Company Llc Nuclear reaction protection system
US6577697B2 (en) * 1997-07-09 2003-06-10 Southwest Research Institute Field analysis of geological samples using delayed neutron activation analysis
US6181759B1 (en) 1999-07-23 2001-01-30 Westinghouse Electric Company Llc Method and apparatus for determining nearness to criticality of a nuclear fueled electric power generating unit
EA005192B1 (ru) * 2000-11-24 2004-12-30 Синельникова-Мурылева, Елена Ирбековна Способ защиты ядерных реакторов и устройство для его осуществления
US6801593B2 (en) * 2002-11-21 2004-10-05 Westinghouse Electric Company Llc Subcritical reactivity measurement method
CA2456284A1 (en) * 2004-01-26 2005-07-26 Ontario Power Generation Inc. Method and system for testing in-core flux detectors
JP4863068B2 (ja) * 2006-09-29 2012-01-25 大日本印刷株式会社 カートン
KR101139619B1 (ko) * 2010-10-13 2012-04-27 한국수력원자력 주식회사 가압경수로 냉각재 내 붕소농도 자동조절 방법 및 장치
US9875818B2 (en) 2012-10-11 2018-01-23 Bwx Technologies, Inc. Fail-safe reactivity compensation method for a nuclear reactor
US9423516B2 (en) * 2013-03-15 2016-08-23 Westinghouse Electric Company Llc Systems and methods for spent fuel pool subcriticality measurement and monitoring
US9761335B2 (en) * 2013-10-21 2017-09-12 Westinghouse Electric Company Llc Method for monitoring boron dilution during a reactor outage
ES2723433T3 (es) 2013-11-26 2019-08-27 Ingenieria Y Marketing S A Dispositivo portátil para la boración de un flujo continuo de agua
US20170263342A1 (en) * 2016-03-10 2017-09-14 Westinghouse Electric Company Llc Real-time reactor coolant system boron concentration monitor utilizing an ultrasonic spectroscpopy system
CN109785980B (zh) * 2019-01-24 2021-01-26 中广核工程有限公司 核电站硼稀释事故处理方法以及系统
EP4415001A1 (en) 2021-10-05 2024-08-14 Ingeniería Y Marketing, S.A. Portable device for the boration of continuously flowing water

Family Cites Families (22)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB827436A (en) * 1958-01-07 1960-02-03 Atomic Energy Authority Uk Improvements in or relating to instrumentation for nuclear reactors
NL280001A (sv) * 1961-06-22 1900-01-01
US3188470A (en) * 1963-03-05 1965-06-08 Charles W Ricker Method of determining the negative reactivity of neutronic multiplying systems
GB1047152A (en) * 1964-01-08 1966-11-02 English Electric Co Ltd Control systems
US3366544A (en) * 1965-07-13 1968-01-30 Atomic Energy Commission Usa Method of and apparatus for controlling start-up of a nuclear reactor
US3424653A (en) * 1967-06-08 1969-01-28 Atomic Energy Commission Method for start-up of a nuclear reactor utilizing a digital computer
US4225390A (en) * 1970-01-14 1980-09-30 Westinghouse Electric Corp. Boron control system for a nuclear power plant
GB1298168A (en) * 1970-05-19 1972-11-29 Westinghouse Electric Corp Control system for a nuclear power plant
US3998693A (en) * 1970-11-23 1976-12-21 Combustion Engineering, Inc. Thermal margin control
DE2137504A1 (de) * 1971-07-27 1973-02-01 Kernforschung Gmbh Ges Fuer Verfahren und vorrichtung zur statischen messung der unterkritikalitaet eines kernreaktors
BE791975A (fr) * 1971-11-30 1973-05-28 Westinghouse Electric Corp Systemes de concentration d'une solution moderatrice utilisee dans une centrale nucleaire a eau sous pression
FR2294473A1 (fr) * 1974-12-11 1976-07-09 Commissariat Energie Atomique Procede et dispositif electronique de commande a securite positive
US4060716A (en) * 1975-05-19 1977-11-29 Rockwell International Corporation Method and apparatus for automatic abnormal events monitor in operating plants
US4104117A (en) * 1977-02-07 1978-08-01 Westinghouse Electric Corp. Nuclear reactor power generation
US4122720A (en) * 1977-04-07 1978-10-31 Alnor Instrument Company Diesel engine exhaust temperature monitor
CA1094698A (en) * 1977-04-21 1981-01-27 Herbert N. Klingbeil System for detection of process trip
ZA782493B (en) * 1978-05-01 1979-12-27 Anglo Amer Corp South Africa Rate of change detection
US4297581A (en) * 1979-01-15 1981-10-27 The Babcock & Wilcox Company Method for the fast and accurate identification of core power in nuclear reactors
US4305786A (en) * 1979-02-12 1981-12-15 Wachter Associates, Inc. Shutdown reactivity meter system for nuclear fuel storage cells
GB2050022A (en) * 1979-05-02 1980-12-31 Moser M Intruder Alarm
GB2074721B (en) * 1980-04-23 1983-09-07 Furnace Construction Co Ltd Smoke sensor apparatus
US4427620A (en) * 1981-02-04 1984-01-24 Westinghouse Electric Corp. Nuclear reactor power supply

Also Published As

Publication number Publication date
FI832876A0 (fi) 1983-08-10
EP0101242A3 (en) 1984-07-04
KR910004191B1 (ko) 1991-06-24
JPS5948694A (ja) 1984-03-19
EP0101242A2 (en) 1984-02-22
US4582672A (en) 1986-04-15
FI81698C (sv) 1990-11-12
ZA835144B (en) 1984-03-28
FI832876A (fi) 1984-02-12
GB8320802D0 (en) 1983-09-21
ES8502283A1 (es) 1984-12-16
GB2125200B (en) 1986-09-10
FR2531802B1 (fr) 1986-12-19
ES524844A0 (es) 1984-12-16
EP0101242B1 (en) 1987-07-15
DE3372555D1 (en) 1987-08-20
GB2125200A (en) 1984-02-29
FR2531802A1 (fr) 1984-02-17
KR840005894A (ko) 1984-11-19

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Owner name: WESTINGHOUSE ELECTRIC CORPORATION