JP2007183268A5 - - Google Patents

Download PDF

Info

Publication number
JP2007183268A5
JP2007183268A5 JP2006350902A JP2006350902A JP2007183268A5 JP 2007183268 A5 JP2007183268 A5 JP 2007183268A5 JP 2006350902 A JP2006350902 A JP 2006350902A JP 2006350902 A JP2006350902 A JP 2006350902A JP 2007183268 A5 JP2007183268 A5 JP 2007183268A5
Authority
JP
Japan
Prior art keywords
operating
plant
variable data
dependent variable
limit
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.)
Granted
Application number
JP2006350902A
Other languages
English (en)
Japanese (ja)
Other versions
JP2007183268A (ja
JP5357389B2 (ja
Filing date
Publication date
Priority claimed from US11/320,919 external-priority patent/US7366273B2/en
Application filed filed Critical
Publication of JP2007183268A publication Critical patent/JP2007183268A/ja
Publication of JP2007183268A5 publication Critical patent/JP2007183268A5/ja
Application granted granted Critical
Publication of JP5357389B2 publication Critical patent/JP5357389B2/ja
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

JP2006350902A 2005-12-30 2006-12-27 原子炉運転に関する作動限界までのマージンを判定する方法 Active JP5357389B2 (ja)

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 (3)

Publication Number Publication Date
JP2007183268A JP2007183268A (ja) 2007-07-19
JP2007183268A5 true JP2007183268A5 (enExample) 2010-02-18
JP5357389B2 JP5357389B2 (ja) 2013-12-04

Family

ID=37908123

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2006350902A Active JP5357389B2 (ja) 2005-12-30 2006-12-27 原子炉運転に関する作動限界までのマージンを判定する方法

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

Similar Documents

Publication Publication Date Title
JP2007183268A5 (enExample)
JP2008139308A5 (enExample)
JP2004198422A5 (enExample)
JP2023521581A (ja) 沸騰水型原子炉（ｂｗｒ）のコンピュータによるシミュレーション方法
JP6099876B2 (ja) 炉心解析プログラムおよび解析装置
JP5357389B2 (ja) 原子炉運転に関する作動限界までのマージンを判定する方法
KR20060049256A (ko) 데이터베이스 생성 방법 및 장치
JP7569405B2 (ja) 炉心計算方法、炉心計算プログラムおよび炉心計算装置
JP2014153285A (ja) 核特性計算結果補正装置および補正方法
Pelykh et al. Grounds of VVER-1000 fuel cladding life control
Tesauro et al. State of the art of wind farm optimization
CN107229771B (zh) 进行核燃料板弹簧压紧力模拟测定的方法
KR101208821B1 (ko) 표준화 연료봉 타입 세트 결정 방법 및 장치
Lu et al. The probabilistic discriminative time-series model with latent variables and its application to industrial chemical process modeling
JP5377420B2 (ja) 誤差推定装置および誤差推定プログラム
CN107153732A (zh) 一种Pin‑by‑Pin分析压水堆堆芯瞬态的方法
JP2011106970A (ja) 誤差推定装置および誤差推定プログラム
Aras et al. Benchmark Study of XFTA and SCRAM Fault Tree Solvers Using Synthetically Generated Fault Trees Models
DeHart et al. Research in support of TREAT kinetics calculations using Rattlesnake/BISON coupling within MAMMOTH
JP4008131B2 (ja) 原子炉炉心性能計算装置
CN119691971B (zh) 一种核反应堆lpd在线保护方法及系统
Mathkari Prototyping a digital twin: using novel machine learning and simulation technologies to forecast accident response in a molten salt reactor
Zhao et al. Shape‐preserving multimoment scheme for advection transport on a hexagonal grid
Xu et al. Two-Step Uncertainty Analysis of Watts Bar Nuclear 1 Cycle 1 with SCALE/PARCS
Zhou et al. Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis