JP2011506920A5 - - Google Patents

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Publication number
JP2011506920A5
JP2011506920A5 JP2010536506A JP2010536506A JP2011506920A5 JP 2011506920 A5 JP2011506920 A5 JP 2011506920A5 JP 2010536506 A JP2010536506 A JP 2010536506A JP 2010536506 A JP2010536506 A JP 2010536506A JP 2011506920 A5 JP2011506920 A5 JP 2011506920A5
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JP
Japan
Prior art keywords
reactor
steps
value
nuclear fuel
nuclear
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JP2010536506A
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English (en)
Japanese (ja)
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JP5753383B2 (ja
JP2011506920A (ja
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Priority claimed from FR0759643A external-priority patent/FR2924852B1/fr
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Publication of JP2011506920A publication Critical patent/JP2011506920A/ja
Publication of JP2011506920A5 publication Critical patent/JP2011506920A5/ja
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Publication of JP5753383B2 publication Critical patent/JP5753383B2/ja
Expired - Fee Related legal-status Critical Current
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JP2010536506A 2007-12-07 2008-11-21 原子炉の操作可能性を表すパラメータの値を決定する方法、決定システム、コンピュータプログラム及び対応する媒体 Expired - Fee Related JP5753383B2 (ja)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
FR0759643A FR2924852B1 (fr) 2007-12-07 2007-12-07 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.
FR0759643 2007-12-07
PCT/FR2008/052104 WO2009071817A2 (fr) 2007-12-07 2008-11-21 Procede de determination de la valeur d'un parametre representatif de la manoeuvrabilite d'un reacteur nucleaire

Publications (3)

Publication Number Publication Date
JP2011506920A JP2011506920A (ja) 2011-03-03
JP2011506920A5 true JP2011506920A5 (enExample) 2014-05-15
JP5753383B2 JP5753383B2 (ja) 2015-07-22

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ID=39551652

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JP2010536506A Expired - Fee Related JP5753383B2 (ja) 2007-12-07 2008-11-21 原子炉の操作可能性を表すパラメータの値を決定する方法、決定システム、コンピュータプログラム及び対応する媒体

Country Status (8)

Country Link
US (1) US9997263B2 (enExample)
EP (1) EP2218078B1 (enExample)
JP (1) JP5753383B2 (enExample)
KR (1) KR20100082804A (enExample)
CN (1) CN101939795B (enExample)
FR (1) FR2924852B1 (enExample)
WO (1) WO2009071817A2 (enExample)
ZA (1) ZA201003901B (enExample)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2950466B1 (fr) * 2009-09-22 2012-01-13 Areva Np Procede d'aide a l'exploitation d'un reacteur nucleaire.
CN105006262B (zh) * 2015-06-15 2017-12-08 中广核研究院有限公司 一种标定核反应堆堆外探测器的方法
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
US10685754B2 (en) * 2016-12-15 2020-06-16 Westinghouse Electric Company Llc Integration of real-time measurements and atomistic modeling to license nuclear components
FR3069694A1 (fr) * 2017-07-28 2019-02-01 Areva Np Procede de surveillance d'un coeur nucleaire comprenant une relaxation d'un seuil, programme, support et reacteur nucleaire 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
FR3077412B1 (fr) 2018-02-01 2021-07-23 Framatome Sa Procede de regulation de parametres operatoires d'un reacteur nucleaire et reacteur nucleaire correspondant
FR3085788B1 (fr) * 2018-09-12 2020-11-27 Framatome Sa Procede de protection d'un reacteur nucleaire et reacteur nucleaire correspondant
JP7267189B2 (ja) * 2019-12-20 2023-05-01 三菱重工業株式会社 出力制限値の解析方法、安全評価方法、炉心設計方法及び解析装置
US20240186028A1 (en) * 2021-04-29 2024-06-06 Virginia Tech Intellectual Properties, Inc. Testing and education microreactor
CN113408147B (zh) * 2021-07-15 2022-07-05 中国科学院近代物理研究所 反应堆燃料性能分析计算方法、系统、存储介质及设备
WO2023014241A1 (ru) * 2021-08-05 2023-02-09 Акционерное Общество "Российский Концерн По Производству Электрической И Тепловой Энергии На Атомных Станциях" Способ корректировки погрешности показаний мощности ядерного реактора

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS597295A (ja) * 1982-07-05 1984-01-14 株式会社日立製作所 原子炉燃料棒健全性監視装置
US4774049A (en) * 1986-04-10 1988-09-27 Westinghouse Electric Corp. Two and three dimensional core power distribution monitor and display
US5091139A (en) * 1989-06-26 1992-02-25 General Electric Company Automated thermal limit monitor
JP3871733B2 (ja) * 1996-06-13 2007-01-24 株式会社東芝 原子炉の炉心監視装置
US6535568B1 (en) * 1999-12-30 2003-03-18 Global Nuclear Fuel -- Americas Llc Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods
US6611572B2 (en) * 2000-12-29 2003-08-26 Global Nuclear Fuel - Americas, L.L.C. Determination of operating limit minimum critical power ratio
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
US8149983B2 (en) * 2006-06-06 2012-04-03 Westinghouse Electric Company Llc Method for analysis of pellet-cladding interaction

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