ES2078946T3 - Monitor automatico de limites termicos. - Google Patents

Monitor automatico de limites termicos.

Info

Publication number
ES2078946T3
ES2078946T3 ES90306864T ES90306864T ES2078946T3 ES 2078946 T3 ES2078946 T3 ES 2078946T3 ES 90306864 T ES90306864 T ES 90306864T ES 90306864 T ES90306864 T ES 90306864T ES 2078946 T3 ES2078946 T3 ES 2078946T3
Authority
ES
Spain
Prior art keywords
flow
limits
thermal
atlm
block
Prior art date
Legal status (The legal status 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 status listed.)
Expired - Lifetime
Application number
ES90306864T
Other languages
English (en)
Inventor
Fred Chia-Chi Chao
William Stewart Rowe
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Application granted granted Critical
Publication of ES2078946T3 publication Critical patent/ES2078946T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

UN MODELO CALCULADO DE DISTRIBUCION EN ESPACIO DE POTENCIA DISPONIBLE DEL REACTOR SE LEE PERIODICAMENTE A LA MEMORIA DEL ORDENADOR BASADA EN EL MICROPROCESADOR Y SE RETIENE EN MEMORIA EN TRES MATRICES DIMENSIONALES. ESTA RETENCION SE PRODUCE ENTRE ACTUALIZACIONES REGULARES DEL ORDEN DE CADA DOS MINUTOS. EL REACTOR ESTA CONVENCIONALMENTE MONITORIZADO EN GRUPOS DE 16 PAQUETES DE COMBUSTIBLE CADA UNO. CADA GRUPO DE 16 PAQUETES SE MONITORIZA EN CUANTO A SU FLUJO DE NEUTRONES TERMICOS MEDIANTE CUATRO CADENAS VERTICALES DE MONITORES DE GAMA LOCAL DE POTENCIA, TENIENDO CADA CADENA UNO DE LOS CUATRO MONITORES DE POTENCIA SITUADO EN CUATRO ELEVACIONES DIFERENTES, QUE EXTIENDEN LA ALTURA DEL NUCLEO ACTIVO. CADA GRUPO DE PAQUETES SE CONTROLA POR CUATRO VARILLAS DE MANDO Y SE DA POR SENTADO QUE ESTA SUJETO A CAMBIO UNIFORME DE FLUJO CON CAMBIO DE FLUJO DEL REACTOR TOTAL. EL MONITOR DE LIMITE TERMICO AUTOMATIZADO (ATLM) TOMA COMO ENTRADAS TODA LA INFORMACION DEL MONITOR DE GAMA DE POTENCIAS PROCEDENTE DEL NUCLEO DEL REACTOR BWR SOBRE UNA BASE CONTINUA A DOS CANALES, UNO DE LOS CUALES PARA DETERMINAR LOS LIMITES OPERATIVOS Y EL OTRO PARA DETERMINAR LOS LIMITES DE SEGURIDAD. ESTAS SEÑALES SE PROCESAN DENTRO DEL SISTEMA, DE CONFORMIDAD CON DIFERENTES REQUERIMIENTOS ALGORITMICOS PARA LA PROTECCION DE LOS LIMITES TERMICOS DE COMBUSTIBLE, ES DECIR, AMPLIFICACION CRITICA MINIMA (MCPR) Y ESTIMACION DE TERMOGENERACION LINEAL MAXIMA (MLHGR). EL SISTEMA TOMA TAMBIEN COMO ENTRADA LOS LIMITES DE PARAMETROS TERMICOS DE NUCLEO ABSOLUTOS ON-LINE, JUNTAMENTE CON UN CONJUNTO DE PARAMETROS INCORPORADOS LLAMADOS FACTORES A Y B, QUE SON FUNCIONES DE POTENCIA DE NUCLEO, Y POSICION DE VARILLAS DE CONTROL, Y LOS DATOS LIMITE TERMICOS OPERATIVOS EN LAS CONDICIONES DE FLUJO Y POTENCIA DE CORRIENTE. BASADO EN LA INFORMACION ANTERIOR, EL SISTEMA CALCULA VALORES DE PUNTOS DE REFERENCIA DE SEÑALES PARA MCPR Y MLHGR RESPECTIVAMENTE. ESTOS VALORES DE PUNTOS DE REFERENCIAS SE COMPARAN CON LAS SEÑALES ATLM INSTANTANEAMENTE EXAMINADAS CONTINUAMENTE PARA DETERMINAR SI DEBE EMITIRSE UN COMANDO DE BLOQUE DE RETIRADA DE VARILLAS DE CONTROL O UN COMANDO DE BLOQUE DE FLUJO DE NUCLEO. SI UN VALOR DE SEÑAL ATLM PROCESADO Y EXPLORADO SE APROXIMA A SU PUNTO DE REFERENCIA, ENTONCES SE EMITE EL BLOQUE DE VARILLAS (O BLOQUE DE FLUJO). ASI SE ASEGURA ENTONCES QUE LOS LIMITES TERMICOS DEL NUCLEO NO SE VIOLAN SOBRE LA RETIRADA DE VARILLAS O CAMBIOS DE FLUJO. ESTE DESCUBRIMIENTO DE LA INVENCION NO DESCRIBE SOLAMENTE LA CONFIGURACION DEL SISTEMA Y LOGICA FUNCIONAL DEL BLOQUE DE VARILLAS Y BLOQUE DE FLUJO, TAMBIEN DESCRIBE LAS BASES DEL DISEÑO DE LOS FACTORES A Y B EN EL ALGORITMO DEL SISTEMA, QUE SON FUNDAMENTALES AL SISTEMA TOTAL ATLM. EL CONCEPTO DE LA CONFIGURACION, LA LOGICA FUNCIONAL Y LA FORMA Y EL DISEÑO DE LOS FACTORES A Y B CONSTITUYEN LA PARTE PRINCIPAL DEL DESCUBRIMIENTO DE LA INVENCION DEL DISEÑO ATLM.
ES90306864T 1989-06-26 1990-06-22 Monitor automatico de limites termicos. Expired - Lifetime ES2078946T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US07/371,365 US5091139A (en) 1989-06-26 1989-06-26 Automated thermal limit monitor

Publications (1)

Publication Number Publication Date
ES2078946T3 true ES2078946T3 (es) 1996-01-01

Family

ID=23463680

Family Applications (1)

Application Number Title Priority Date Filing Date
ES90306864T Expired - Lifetime ES2078946T3 (es) 1989-06-26 1990-06-22 Monitor automatico de limites termicos.

Country Status (5)

Country Link
US (1) US5091139A (es)
EP (1) EP0405863B1 (es)
JP (1) JPH0769451B2 (es)
DE (1) DE69022305T2 (es)
ES (1) ES2078946T3 (es)

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JP3224810B2 (ja) * 1990-10-04 2001-11-05 株式会社東芝 燃料集合体の限界出力比計算装置
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US5555279A (en) * 1994-11-16 1996-09-10 Nir; Israel System for monitoring and controlling nuclear reactors
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US5930779A (en) * 1997-03-25 1999-07-27 Mci Communications Corporation Web based system and method to automate storage of power plant data and calculation of battery reserves
US6169987B1 (en) 1997-03-25 2001-01-02 Mci Communications Corporation System and method to automate equipment placement at remote sites
US6952705B2 (en) 1997-03-25 2005-10-04 Mci, Inc. Method, system and program product that utilize a hierarchical conceptual framework to model an environment containing a collection of items
US5912933A (en) * 1997-12-04 1999-06-15 General Electric Company Method and system for direct evaluation of operating limit minimum critical power ratios for boiling water reactors
TW429381B (en) 1998-04-28 2001-04-11 Siemens Ag Method and device for supervising the power increase during the operation of nuclear reactors (diversified excursion supervision)
JP3924932B2 (ja) * 1998-07-02 2007-06-06 株式会社日立製作所 原子力プラントの制御システム
US6748348B1 (en) 1999-12-30 2004-06-08 General Electric Company Design method for nuclear reactor fuel management
US6611572B2 (en) * 2000-12-29 2003-08-26 Global Nuclear Fuel - Americas, L.L.C. Determination of operating limit minimum critical power ratio
TW594791B (en) 2001-09-27 2004-06-21 Toshiba Corp Incore monitoring method and incore monitoring equipment
US20030086520A1 (en) * 2001-11-07 2003-05-08 Russell William Earl System and method for continuous optimization of control-variables during operation of a nuclear reactor
US7487133B2 (en) * 2002-09-19 2009-02-03 Global Nuclear Fuel - Americas, Llc Method and apparatus for adaptively determining weight factors within the context of an objective function
FR2846139B1 (fr) 2002-10-21 2005-02-18 Framatome Anp Procede de determination d'une valeur limite d'un parametre de fonctionnement d'un reacteur nucleaire, programme et support correspondants
US6862329B1 (en) * 2003-10-06 2005-03-01 Global Nuclear Fuel-Americas Llc In-cycle shuffle
US8041548B2 (en) 2004-12-30 2011-10-18 Global Nuclear Fuels-Americas, LLC Method and apparatus for evaluating a proposed solution to a constraint problem for a nuclear reactor involving channel deformation
US7991844B2 (en) * 2005-07-12 2011-08-02 International Business Machines Corporation Method, system and computer program product for processing a plurality of electronic mail files
JP4594819B2 (ja) * 2005-07-29 2010-12-08 株式会社東芝 制御棒引抜監視装置
EP1775732B1 (en) * 2005-08-31 2013-07-31 Westinghouse Electric Sweden AB A method of estimating dryout properties in a nuclear light water reactor
US7366273B2 (en) * 2005-12-30 2008-04-29 General Electric Company Method of determining margins to operating limits for nuclear reactor operation
US8842802B2 (en) * 2006-10-16 2014-09-23 Global Nuclear Fuel-Americas, Llc. Fuel rods for nuclear reactor fuel assemblies and methods of manufacturing thereof
SE532185C2 (sv) * 2007-04-10 2009-11-10 Westinghouse Electric Sweden Förfarande för att driva en reaktor hos en kärnanläggning
EP2048670B1 (en) 2007-10-10 2015-05-20 Westinghouse Electric Sweden AB Methods and devices relating to a nuclear light water reactor of the boiling water kind
FR2924852B1 (fr) * 2007-12-07 2010-02-19 Areva Np Procede de determination de la valeur d'un parametre representatif de la manoeuvrabilite d'un reacteur nucleaire, systeme de determination, programme d'ordinateur et support correspondant.
US8433029B2 (en) 2007-12-14 2013-04-30 Global Nuclear Fuel—Americas, LLC Determination of safety limit minimum critical power ratio
JP5191342B2 (ja) * 2008-10-09 2013-05-08 中国電力株式会社 原子炉の制御棒引抜監視装置
FR2946454B1 (fr) * 2009-06-08 2011-07-22 Areva Np Procede de determination de valeurs limites d'exploitation d'un reacteur nucleaire pour eviter l'endommagement par interaction pastille-gaine.
JP2012150088A (ja) * 2011-01-21 2012-08-09 Toshiba Corp 振動領域モニタおよびその健全性確認方法
US20130266107A1 (en) 2012-03-16 2013-10-10 Westinghouse Electric Company Llc Methods for protection of nuclear reactors from thermal hydraulic/neutronic core instability
US20140376678A1 (en) * 2013-06-25 2014-12-25 Robert H. Leyse Method of and Apparatus for Monitoring a Nuclear Reactor Core Under Normal and Accident Conditions
JP6453262B2 (ja) * 2016-03-09 2019-01-16 日立Ｇｅニュークリア・エナジー株式会社 制御棒操作監視方法及び制御棒操作監視システム
FR3053150B1 (fr) * 2016-06-22 2020-09-18 Areva Np Procede de calcul d'une marge ipg associee a un plan de chargement d'un reacteur nucleaire, systeme, programme d"'ordinateur et support associes
FR3075449B1 (fr) 2017-12-18 2020-01-10 Areva Np Procede de determination d'au moins une valeur limite d'au moins un parametre de fonctionnement d'un reacteur nucleaire, programme d'ordinateur et systeme electronique associes
KR102034830B1 (ko) * 2018-01-05 2019-10-21 한국수력원자력 주식회사 중성자 고출력 검출기 고장 모니터링 방법
CN109215820B (zh) * 2018-08-14 2019-11-26 中广核核电运营有限公司 核电站蒸发器汽水流量测量通道比较方法及系统
CN109243641B (zh) * 2018-10-18 2022-04-22 中国核动力研究设计院 用于压水堆失水事故的反应堆压力容器实验模拟体
CN113421676B (zh) * 2021-06-18 2022-05-10 中国核动力研究设计院 一种核电厂事故规程整定值的确定方法及装置
CN115295179B (zh) * 2022-08-22 2023-12-12 中国原子能科学研究院 反应堆功率测量的补偿方法

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US5024801A (en) * 1989-05-01 1991-06-18 Westinghouse Electric Corp. Reactor core model update system

Also Published As

Publication number Publication date
JPH0769451B2 (ja) 1995-07-31
JPH0365693A (ja) 1991-03-20
DE69022305D1 (de) 1995-10-19
US5091139A (en) 1992-02-25
EP0405863A3 (en) 1991-11-21
DE69022305T2 (de) 1996-04-04
EP0405863A2 (en) 1991-01-02
EP0405863B1 (en) 1995-09-13

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