WO2009001004A3 - Procede de determination d'une composante d'incertitude relative a la distribution de puissance dans le coeur d'un reacteur nucleaire - Google Patents

Procede de determination d'une composante d'incertitude relative a la distribution de puissance dans le coeur d'un reacteur nucleaire Download PDF

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Publication number
WO2009001004A3
WO2009001004A3 PCT/FR2008/051001 FR2008051001W WO2009001004A3 WO 2009001004 A3 WO2009001004 A3 WO 2009001004A3 FR 2008051001 W FR2008051001 W FR 2008051001W WO 2009001004 A3 WO2009001004 A3 WO 2009001004A3
Authority
WO
WIPO (PCT)
Prior art keywords
power distribution
nuclear reactor
determining
uncertainty component
reactor core
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.)
Ceased
Application number
PCT/FR2008/051001
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English (en)
Other versions
WO2009001004A2 (fr
Inventor
Gerard Rio
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.)
Areva NP SAS
Original Assignee
Areva NP SAS
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 Areva NP SAS filed Critical Areva NP SAS
Priority to US12/663,578 priority Critical patent/US20100226468A1/en
Priority to CN200880025011A priority patent/CN101755308A/zh
Priority to EP08805938A priority patent/EP2176866A2/fr
Priority to JP2010510860A priority patent/JP2010529448A/ja
Publication of WO2009001004A2 publication Critical patent/WO2009001004A2/fr
Publication of WO2009001004A3 publication Critical patent/WO2009001004A3/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

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

Abstract

La présente invention a pour objet un procédé permettant d'obtenir une composante (RUN2p ) d'incertitude de propagation d'erreur (206) pour tout réacteur nucléaire, même ceux destinés à être équipés d'un système d'instrumentation de mesure pour lequel il n'existe pas de retour d'exploitation avec le système considéré. A cet effet, dans l'invention, on propose d'utiliser des données (200) provenant d'un retour d'expérience acquis avec un système d'instrumentation de référence, par exemple le système RIC. Le retour d'expérience est utilisé pour appliquer à un modèle théorique de distribution de puissance (201 ) des perturbations dont l'amplitude et la répartition dans l'espace sont telles que les écarts observés (203) entre le modèle théorique perturbé et le modèle théorique directement issu du calcul sont représentatifs de ceux observés dans la réalité.
PCT/FR2008/051001 2007-06-08 2008-06-05 Procede de determination d'une composante d'incertitude relative a la distribution de puissance dans le coeur d'un reacteur nucleaire Ceased WO2009001004A2 (fr)

Priority Applications (4)

Application Number Priority Date Filing Date Title
US12/663,578 US20100226468A1 (en) 2007-06-08 2008-06-05 Method for determining an uncertainty component relating to power distribution in a nuclear reactor core
CN200880025011A CN101755308A (zh) 2007-06-08 2008-06-05 确定关于核反应堆堆芯中功率分布的不确定性分量的方法
EP08805938A EP2176866A2 (fr) 2007-06-08 2008-06-05 Procede de determination d'une composante d'incertitude relative a la distribution de puissance dans le coeur d'un reacteur nucleaire
JP2010510860A JP2010529448A (ja) 2007-06-08 2008-06-05 原子炉心内の出力分布に関連する不確かさ成分を算出する方法

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR0755584A FR2917228A1 (fr) 2007-06-08 2007-06-08 Procede de determination d'une composante d'incertitude relative a la distribution de puissance dans le coeur d'un reacteur nucleaire
FR0755584 2007-06-08

Publications (2)

Publication Number Publication Date
WO2009001004A2 WO2009001004A2 (fr) 2008-12-31
WO2009001004A3 true WO2009001004A3 (fr) 2009-02-19

Family

ID=38876798

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/FR2008/051001 Ceased WO2009001004A2 (fr) 2007-06-08 2008-06-05 Procede de determination d'une composante d'incertitude relative a la distribution de puissance dans le coeur d'un reacteur nucleaire

Country Status (8)

Country Link
US (1) US20100226468A1 (fr)
EP (1) EP2176866A2 (fr)
JP (1) JP2010529448A (fr)
KR (1) KR20100030649A (fr)
CN (1) CN101755308A (fr)
FR (1) FR2917228A1 (fr)
RU (1) RU2009148714A (fr)
WO (1) WO2009001004A2 (fr)

Families Citing this family (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102411997B (zh) * 2011-10-25 2014-04-02 清华大学 高温气冷堆功率控制方法及系统
CN104036837B (zh) * 2014-06-09 2016-08-24 中科华核电技术研究院有限公司 通量图时刻及连续时刻堆芯监测功率不确定分析方法
US20150364225A1 (en) * 2014-06-13 2015-12-17 Korea Hydro & Nuclear Power Co., Ltd. Method of synthesizing nuclear reactor power distribution using optimized nonlinear basis function
CN107689256B (zh) * 2017-09-19 2019-06-07 中国核动力研究设计院 一种核反应堆次临界度测量方法
CN107644133B (zh) * 2017-09-19 2021-05-14 中国核动力研究设计院 一种核反应堆堆芯吊篮振动刻度因子计算方法
FR3085787B1 (fr) * 2018-09-12 2020-10-23 Framatome Sa Procede d'exploitation d'un reacteur nucleaire avec calcul du rftc en ligne, reacteur nucleaire correspondant
CN109543941B (zh) * 2018-10-15 2022-04-19 中国核电工程有限公司 一种基于安全壳工况确定核电厂事故策略定值的方法
CN111370152B (zh) * 2020-03-10 2021-11-23 中国原子能科学研究院 避免反应堆核测量装置换挡引起功率扰动的方法及装置
CN111554418B (zh) * 2020-05-18 2022-04-29 中国核动力研究设计院 一种核反应堆外推临界方法
CN112069441B (zh) * 2020-07-16 2022-03-18 中山大学 一种堆芯瞬态三维功率分布在线重构方法
CN111814343B (zh) * 2020-07-16 2022-03-18 中山大学 综合堆内外探测器测量值的堆芯功率分布在线重构方法
CN112133462B (zh) * 2020-09-24 2022-07-29 中国核动力研究设计院 一种临界装置功率刻度方法
CN115327461A (zh) * 2022-07-04 2022-11-11 中广核陆丰核电有限公司 堆外核测系统功率量程修正参数的修改方法和系统
CN115408861B (zh) * 2022-08-31 2023-11-10 中国核动力研究设计院 用于反应堆运行参数优化的数据同化方法、系统及终端
CN115862912B (zh) * 2023-02-27 2023-05-02 西安交通大学 一种动态氙条件下压水堆堆芯功率分布测量方法
CN116682585B (zh) * 2023-06-19 2025-11-28 中广核研究院有限公司 堆芯功率分布测量不确定性的分析方法、装置和设备
CN119397124B (zh) * 2024-09-20 2025-11-21 华能核能技术研究院有限公司 反应堆堆芯功率分布在线监测敏感性系数计算方法及系统

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0241301A2 (fr) * 1986-04-10 1987-10-14 Westinghouse Electric Corporation Dispositif de surveillance de la distribution de la puissance axiale et affichage utilisant des données provenant des détecteurs et thermocouples hors coeur
US4774049A (en) * 1986-04-10 1988-09-27 Westinghouse Electric Corp. Two and three dimensional core power distribution monitor and display
EP1197970A1 (fr) * 2000-10-11 2002-04-17 Westinghouse Electric Company LLC Procédé d'étalonnage de thermocouples dans un réacteur nucléaire

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0241301A2 (fr) * 1986-04-10 1987-10-14 Westinghouse Electric Corporation Dispositif de surveillance de la distribution de la puissance axiale et affichage utilisant des données provenant des détecteurs et thermocouples hors coeur
US4774049A (en) * 1986-04-10 1988-09-27 Westinghouse Electric Corp. Two and three dimensional core power distribution monitor and display
EP1197970A1 (fr) * 2000-10-11 2002-04-17 Westinghouse Electric Company LLC Procédé d'étalonnage de thermocouples dans un réacteur nucléaire

Also Published As

Publication number Publication date
WO2009001004A2 (fr) 2008-12-31
RU2009148714A (ru) 2011-07-20
JP2010529448A (ja) 2010-08-26
KR20100030649A (ko) 2010-03-18
US20100226468A1 (en) 2010-09-09
FR2917228A1 (fr) 2008-12-12
EP2176866A2 (fr) 2010-04-21
CN101755308A (zh) 2010-06-23

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