KR20100082804A - 원자로의 작동성을 나타내는 매개 변수의 값을 결정하기 위한 방법, 결정 시스템, 컴퓨터 프로그램 및 대응 매체 - Google Patents

원자로의 작동성을 나타내는 매개 변수의 값을 결정하기 위한 방법, 결정 시스템, 컴퓨터 프로그램 및 대응 매체 Download PDF

Info

Publication number
KR20100082804A
KR20100082804A KR1020107012413A KR20107012413A KR20100082804A KR 20100082804 A KR20100082804 A KR 20100082804A KR 1020107012413 A KR1020107012413 A KR 1020107012413A KR 20107012413 A KR20107012413 A KR 20107012413A KR 20100082804 A KR20100082804 A KR 20100082804A
Authority
KR
South Korea
Prior art keywords
reactor
value
determining
operability
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.)
Ceased
Application number
KR1020107012413A
Other languages
English (en)
Korean (ko)
Inventor
길스 안드레포여드
브루노 줄리앙
장-루시앙 모르레밧
Original Assignee
아레바 엔피
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 아레바 엔피 filed Critical 아레바 엔피
Publication of KR20100082804A publication Critical patent/KR20100082804A/ko
Ceased legal-status Critical Current

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)
KR1020107012413A 2007-12-07 2008-11-21 원자로의 작동성을 나타내는 매개 변수의 값을 결정하기 위한 방법, 결정 시스템, 컴퓨터 프로그램 및 대응 매체 Ceased KR20100082804A (ko)

Applications Claiming Priority (2)

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

Publications (1)

Publication Number Publication Date
KR20100082804A true KR20100082804A (ko) 2010-07-19

Family

ID=39551652

Family Applications (1)

Application Number Title Priority Date Filing Date
KR1020107012413A Ceased KR20100082804A (ko) 2007-12-07 2008-11-21 원자로의 작동성을 나타내는 매개 변수의 값을 결정하기 위한 방법, 결정 시스템, 컴퓨터 프로그램 및 대응 매체

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)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20190087641A (ko) * 2016-12-15 2019-07-24 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨 원자핵 구성요소를 허가하기 위한 실시간 측정 및 원자 모델링의 통합

Families Citing this family (11)

* 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
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

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20190087641A (ko) * 2016-12-15 2019-07-24 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨 원자핵 구성요소를 허가하기 위한 실시간 측정 및 원자 모델링의 통합

Also Published As

Publication number Publication date
EP2218078A2 (fr) 2010-08-18
JP5753383B2 (ja) 2015-07-22
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
CN101939795B (zh) 2014-01-22
US9997263B2 (en) 2018-06-12
WO2009071817A2 (fr) 2009-06-11
EP2218078B1 (fr) 2014-01-08

Similar Documents

Publication Publication Date Title
KR20100082804A (ko) 원자로의 작동성을 나타내는 매개 변수의 값을 결정하기 위한 방법, 결정 시스템, 컴퓨터 프로그램 및 대응 매체
CN110970142B (zh) 一种压水堆大破口失水事故始发应急工况预测方法
JP2018537660A (ja) 迅速応答自己給電型炉内検出器を用いる臨界未満反応度監視装置
Pastore et al. Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Fuel modeling developments and simulation of integral experiments
Wang et al. The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC
Lemes et al. Inclusion of models to describe severe accident conditions in the fuel simulation code DIONISIO
Capps et al. BISON validation to in situ cladding burst test and high-burnup LOCA experiments
Wang et al. Comparison of CORA & MELCOR core degradation simulation and the MELCOR oxidation model
CN112771625B (zh) 用于保护核反应堆的方法和对应的核反应堆
Jernkvist Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik
JP7175960B2 (ja) 閾値の緩和を含む核炉心を監視するための方法、および関連するプログラム、保持体、核原子炉
Massih et al. Assessment of data and criteria for cladding burst in loss-of-coolant accidents
Vanier et al. Superphénix reactivity and feedback coefficients
Manngård et al. Evaluation of loss-of-coolant accident simulation tests with the fuel rod analysis code FRAPTRAN-1.4
Svanholm et al. Halden reactors IFA-511.2 and IFA-54x: Experimental series under adverse core cooling conditions
Chang et al. Whole-core damage analysis of EBR-II driver fuel elements following SHRT program
RU2772793C2 (ru) Способ мониторинга активной зоны, включающий в себя ослабление порога, и соответствующие программа, носитель информации и ядерный реактор
Huang et al. Calculation of boron concentration dependent reactivity versus moderator density curve with application on ATWS analysis for Maanshan PWR plant
Brown et al. Physics Testing at Fort St. Vrain—A Review
Kaliatka et al. Modelling of QUENCH 03 and QUENCH 06 experiments using RELAP/SCDAPSIM code
Williamson et al. BISON Validation for LOCA and PCMI Behaviour Using Measurements From the Halden Reactor Project
Lisowski et al. Experimental observations of natural circulation flow in the nstf at steady-state conditions
Dolganov et al. MODELLING OF PARAMETER-SF4 EXPERIMENT WITH SOCRAT/V1 CODE
Paraschiv et al. Simulation of CANDU Fuel Behaviour into In-Reactor LOCA Tests
Guidez et al. Neutronics

Legal Events

Date Code Title Description
PA0105 International application

Patent event date: 20100604

Patent event code: PA01051R01D

Comment text: International Patent Application

PG1501 Laying open of application
A201 Request for examination
PA0201 Request for examination

Patent event code: PA02012R01D

Patent event date: 20131022

Comment text: Request for Examination of Application

E902 Notification of reason for refusal
PE0902 Notice of grounds for rejection

Comment text: Notification of reason for refusal

Patent event date: 20141023

Patent event code: PE09021S01D

E601 Decision to refuse application
PE0601 Decision on rejection of patent

Patent event date: 20150730

Comment text: Decision to Refuse Application

Patent event code: PE06012S01D

Patent event date: 20141023

Comment text: Notification of reason for refusal

Patent event code: PE06011S01I

J201 Request for trial against refusal decision
PJ0201 Trial against decision of rejection

Patent event date: 20151012

Comment text: Request for Trial against Decision on Refusal

Patent event code: PJ02012R01D

Patent event date: 20150730

Comment text: Decision to Refuse Application

Patent event code: PJ02011S01I

Appeal kind category: Appeal against decision to decline refusal

Appeal identifier: 2015101005995

Request date: 20151012

J301 Trial decision

Free format text: TRIAL NUMBER: 2015101005995; TRIAL DECISION FOR APPEAL AGAINST DECISION TO DECLINE REFUSAL REQUESTED 20151012

Effective date: 20161228

PJ1301 Trial decision

Patent event code: PJ13011S01D

Patent event date: 20161228

Comment text: Trial Decision on Objection to Decision on Refusal

Appeal kind category: Appeal against decision to decline refusal

Request date: 20151012

Decision date: 20161228

Appeal identifier: 2015101005995