KR20070072399A - 동작 마진 결정 방법 - Google Patents

동작 마진 결정 방법 Download PDF

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Publication number
KR20070072399A
KR20070072399A KR1020060136853A KR20060136853A KR20070072399A KR 20070072399 A KR20070072399 A KR 20070072399A KR 1020060136853 A KR1020060136853 A KR 1020060136853A KR 20060136853 A KR20060136853 A KR 20060136853A KR 20070072399 A KR20070072399 A KR 20070072399A
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KR
South Korea
Prior art keywords
operating
power plant
variable data
dependent variable
reactor
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.)
Withdrawn
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KR1020060136853A
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English (en)
Korean (ko)
Inventor
윌리암 이얼 2세 루셀
루셀 모간 파우셋
윌리암 찰스 클린
데이비드 조셉 크로파제크
글렌 에이 왓포드
루카스 트로스만
스티븐 배리 서튼
크리스틴 카를로스 오야준
Original Assignee
글로벌 뉴클리어 퓨얼-어메리카스, 엘엘씨
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.)
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Publication date
Application filed by 글로벌 뉴클리어 퓨얼-어메리카스, 엘엘씨 filed Critical 글로벌 뉴클리어 퓨얼-어메리카스, 엘엘씨
Publication of KR20070072399A publication Critical patent/KR20070072399A/ko
Withdrawn legal-status Critical Current

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    • 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
    • G21D3/08Regulation of any parameters in the plant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • 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

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
KR1020060136853A 2005-12-30 2006-12-28 동작 마진 결정 방법 Withdrawn KR20070072399A (ko)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US11/320,919 2005-12-30
US11/320,919 US7366273B2 (en) 2005-12-30 2005-12-30 Method of determining margins to operating limits for nuclear reactor operation

Publications (1)

Publication Number Publication Date
KR20070072399A true KR20070072399A (ko) 2007-07-04

Family

ID=37908123

Family Applications (1)

Application Number Title Priority Date Filing Date
KR1020060136853A Withdrawn KR20070072399A (ko) 2005-12-30 2006-12-28 동작 마진 결정 방법

Country Status (7)

Country Link
US (1) US7366273B2 (enExample)
EP (1) EP1804255A3 (enExample)
JP (1) JP5357389B2 (enExample)
KR (1) KR20070072399A (enExample)
CN (1) CN101034595A (enExample)
MX (1) MXPA06015255A (enExample)
TW (1) TWI389138B (enExample)

Families Citing this family (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2077561A1 (en) * 2008-01-01 2009-07-08 Institute of Nuclear Energy Research Atomic Energy Council, Executive Yuan Thermal limit analysis with hot-channel model for boiling water reactors
US9424376B2 (en) * 2011-11-18 2016-08-23 Terrapower, Llc Enhanced neutronics systems
US9031892B2 (en) 2012-04-19 2015-05-12 Invensys Systems, Inc. Real time safety management system and method
US10310457B2 (en) * 2014-11-24 2019-06-04 Aspen Technology, Inc. Runtime modeling approach to updating refinery planning models
RU2589038C1 (ru) * 2015-06-10 2016-07-10 Федеральное государственное бюджетное учреждение "Национальный исследовательский центр "Курчатовский институт" Способ регулирования параметров ядерного реактора
CN105469325B (zh) * 2015-12-21 2022-04-08 云南电网有限责任公司电力科学研究院 一种确定火电机组负荷稳定状态的方法及系统
JP7023165B2 (ja) * 2018-04-16 2022-02-21 三菱重工業株式会社 原子炉の熱出力評価方法、原子炉の熱出力評価装置及び原子炉の熱出力評価プログラム、原子力設備の運転管理方法、原子力設備の運転管理装置、原子力設備の運転管理プログラム
FR3085788B1 (fr) * 2018-09-12 2020-11-27 Framatome Sa Procede de protection d'un reacteur nucleaire et reacteur nucleaire correspondant
CN110119878B (zh) * 2019-04-09 2022-12-16 华能山东石岛湾核电有限公司 一种适用于特定电厂临时性变更的风险指引决策方法
JP7252100B2 (ja) * 2019-09-04 2023-04-04 原子燃料工業株式会社 炉心計算方法、炉心計算プログラムおよび炉心計算装置
DE102020004277A1 (de) * 2020-07-13 2022-01-13 BTB Jansky GmbH Verfahren zur Simulation von Betriebs/Komponentenzuständen von Anlagen, insbesondere von Kraftwerksanlagen
CN111899905B (zh) * 2020-08-05 2022-11-01 哈尔滨工程大学 一种基于核动力装置的故障诊断方法及系统
CN113157790B (zh) * 2021-04-20 2022-10-11 核工业西南物理研究院 一种核聚变曲线编辑方法、系统、终端及介质
CN113568386B (zh) * 2021-07-30 2023-02-28 西安热工研究院有限公司 一种基于区间估计的火电机组全工况大数据分析方法
CN119601272B (zh) * 2024-10-24 2025-10-17 中国核动力研究设计院 一种多环路反应堆系统运行方法、装置、设备及介质
CN120409281B (zh) * 2025-06-11 2025-09-12 深圳大学 一种高效核反应堆安全裕度评估方法、系统、终端设备及计算机程序产品

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5091139A (en) * 1989-06-26 1992-02-25 General Electric Company Automated thermal limit monitor
JP2975654B2 (ja) * 1990-08-30 1999-11-10 株式会社東芝 炉心監視装置
SE509235C2 (sv) * 1993-05-11 1998-12-21 Asea Atom Ab Förfarande för övervakning med avseende på dryout av en kokarreaktor
JPH08179078A (ja) * 1994-12-19 1996-07-12 Toshiba Corp 原子力発電所監視装置
US5631937A (en) * 1995-11-15 1997-05-20 Westinghouse Electric Corporation Method and apparatus for protecting a PWR from departure from nucleate boiling and hot leg boiling
JP3871733B2 (ja) * 1996-06-13 2007-01-24 株式会社東芝 原子炉の炉心監視装置
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
US6748348B1 (en) * 1999-12-30 2004-06-08 General Electric Company Design method for nuclear reactor fuel management
KR100399759B1 (ko) * 2000-11-01 2003-09-29 한국과학기술원 원자력 발전소의 디지털 온라인 능동 시험 발전소 보호시스템 및 그 방법
US6611572B2 (en) * 2000-12-29 2003-08-26 Global Nuclear Fuel - Americas, L.L.C. Determination of operating limit minimum critical power ratio
US7200541B2 (en) * 2002-12-23 2007-04-03 Global Nuclear Fuel-Americas, Llc Method and arrangement for determining nuclear reactor core designs
JP4617503B2 (ja) * 2003-12-15 2011-01-26 株式会社グローバル・ニュークリア・フュエル・ジャパン 炉心監視システム
JP2005331290A (ja) * 2004-05-18 2005-12-02 Toshiba Corp Bwrプラントの運転制御システム
JP2005345421A (ja) * 2004-06-07 2005-12-15 Toshiba Corp 炉内構造物の欠陥裕度評価方法

Also Published As

Publication number Publication date
EP1804255A3 (en) 2010-07-07
US20070153958A1 (en) 2007-07-05
MXPA06015255A (es) 2008-10-17
TW200741745A (en) 2007-11-01
CN101034595A (zh) 2007-09-12
JP2007183268A (ja) 2007-07-19
JP5357389B2 (ja) 2013-12-04
EP1804255A2 (en) 2007-07-04
US7366273B2 (en) 2008-04-29
TWI389138B (zh) 2013-03-11

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Legal Events

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PA0109 Patent application

Patent event code: PA01091R01D

Comment text: Patent Application

Patent event date: 20061228

PG1501 Laying open of application
PC1203 Withdrawal of no request for examination
WITN Application deemed withdrawn, e.g. because no request for examination was filed or no examination fee was paid