CN101939795B - 确定表征核反应堆的可操作性的参数的值的方法、确定系统、计算机程序和相应的载体 - Google Patents

确定表征核反应堆的可操作性的参数的值的方法、确定系统、计算机程序和相应的载体 Download PDF

Info

Publication number
CN101939795B
CN101939795B CN200880126186.8A CN200880126186A CN101939795B CN 101939795 B CN101939795 B CN 101939795B CN 200880126186 A CN200880126186 A CN 200880126186A CN 101939795 B CN101939795 B CN 101939795B
Authority
CN
China
Prior art keywords
reactor
value
involucrum
nuclear fuel
fuel rod
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.)
Active
Application number
CN200880126186.8A
Other languages
English (en)
Chinese (zh)
Other versions
CN101939795A (zh
Inventor
G·安德烈·普约
B·朱利安
J-L·穆勒瓦
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
Framatome ANP 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 Framatome ANP SAS filed Critical Framatome ANP SAS
Publication of CN101939795A publication Critical patent/CN101939795A/zh
Application granted granted Critical
Publication of CN101939795B publication Critical patent/CN101939795B/zh
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • 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

  • 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)
CN200880126186.8A 2007-12-07 2008-11-21 确定表征核反应堆的可操作性的参数的值的方法、确定系统、计算机程序和相应的载体 Active CN101939795B (zh)

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 (2)

Publication Number Publication Date
CN101939795A CN101939795A (zh) 2011-01-05
CN101939795B true CN101939795B (zh) 2014-01-22

Family

ID=39551652

Family Applications (1)

Application Number Title Priority Date Filing Date
CN200880126186.8A Active CN101939795B (zh) 2007-12-07 2008-11-21 确定表征核反应堆的可操作性的参数的值的方法、确定系统、计算机程序和相应的载体

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

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0405863A2 (en) * 1989-06-26 1991-01-02 General Electric Company Automated thermal limit monitor
EP1113455A1 (en) * 1999-12-30 2001-07-04 General Electric Company Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods
EP1221701A1 (en) * 2000-12-29 2002-07-10 Global Nuclear Fuel-Americas, LLC Determination of operating limit minimum critical power ratio
CN1714410A (zh) * 2002-10-21 2005-12-28 法玛通Anp公司 用于建立核反应堆的操作参数的限制值的方法、相应的系统、计算机程序和介质

Family Cites Families (4)

* 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
JP3871733B2 (ja) * 1996-06-13 2007-01-24 株式会社東芝 原子炉の炉心監視装置
US8149983B2 (en) * 2006-06-06 2012-04-03 Westinghouse Electric Company Llc Method for analysis of pellet-cladding interaction

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0405863A2 (en) * 1989-06-26 1991-01-02 General Electric Company Automated thermal limit monitor
EP1113455A1 (en) * 1999-12-30 2001-07-04 General Electric Company Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods
EP1221701A1 (en) * 2000-12-29 2002-07-10 Global Nuclear Fuel-Americas, LLC Determination of operating limit minimum critical power ratio
CN1714410A (zh) * 2002-10-21 2005-12-28 法玛通Anp公司 用于建立核反应堆的操作参数的限制值的方法、相应的系统、计算机程序和介质

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
JP特开平10-2987A 1998.01.06

Also Published As

Publication number Publication date
EP2218078A2 (fr) 2010-08-18
JP5753383B2 (ja) 2015-07-22
KR20100082804A (ko) 2010-07-19
WO2009071817A3 (fr) 2009-08-13
US20100260300A1 (en) 2010-10-14
ZA201003901B (en) 2011-03-30
CN101939795A (zh) 2011-01-05
FR2924852A1 (fr) 2009-06-12
JP2011506920A (ja) 2011-03-03
FR2924852B1 (fr) 2010-02-19
US9997263B2 (en) 2018-06-12
WO2009071817A2 (fr) 2009-06-11
EP2218078B1 (fr) 2014-01-08

Similar Documents

Publication Publication Date Title
CN101939795B (zh) 确定表征核反应堆的可操作性的参数的值的方法、确定系统、计算机程序和相应的载体
Rempe et al. Instrumentation performance during the TMI-2 accident
Williams et al. MHTGR development in the United States
US20060129362A1 (en) Method for determining threshold value of a nuclear reactor operating parameter, corresponding system, computer programme and support
Gou et al. Preliminary phenomena identification and ranking tables on the subject of the High Temperature Gas-cooled Reactor-Pebble Bed Module thermal fluids and accident analysis
US12051515B2 (en) Method for protecting a nuclear reactor and corresponding nuclear reactor
Gourdon et al. An overview of Superphenix commissioning tests
Gharari et al. Study the effects of various parameters on hydrogen production in the WWER1000/V446
Vanier et al. Superphénix reactivity and feedback coefficients
Wieckhorst et al. AREVA’s Test Facility KATHY: Robust Critical Heat Flux Measurements, a Prerequisite for Reliable CHF Prediction
Jensen et al. The TREAT experiment legacy supporting LWR fuel technology
Zhang et al. Temperature analysis of the HTR-10 after full load rejection
JP2001099976A (ja) 原子炉の熱的運転余裕監視装置および熱的運転余裕監視方法
Carelli IRIS final technical progress report
Sakai et al. Activities of the safety and operation project for the international research and development of the sodium-cooled fast reactor in the generation IV international forum
Jasiulevicius STR on Pellet-Cladding Interactions (PCI and PCMI): Progress in the Nuclear Industry
Karam Application of a Graded Approach to Support the National Research Universal Reactor U-2 Experimental Loop Return to Service
Nijhawan Computer code ROSHNI's preductions of CANDU severe accident progression and its confirmation of severity of reactor design omissions, source term vulnerabilities, and avoidable risks
Armstrong et al. Coupled Thermal-Hydraulic and Fuel Performance Simulations of the TWIST LOCA Commissioning Test Series in TREAT
Folsom et al. BISON Capability, Validation and Demonstration for Reactivity-Initiated Accidents
Coucil et al. Development of a new WWER-440 fuel design
Lianjie et al. Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients
Axford et al. Final safety and hazards analysis for the Battelle LOCA simulation tests in the NRU reactor
Rempe et al. Qualification of data obtained during a severe accident. Illustrative examples from TMI-2 evaluations
Burtt Overview of the LOFT experimental program

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant