MXPA06015255A - Metodo para determinar imagenes para limites de operación para una operacion de reactor nuclear. - Google Patents
Metodo para determinar imagenes para limites de operación para una operacion de reactor nuclear.Info
- Publication number
- MXPA06015255A MXPA06015255A MXPA06015255A MXPA06015255A MXPA06015255A MX PA06015255 A MXPA06015255 A MX PA06015255A MX PA06015255 A MXPA06015255 A MX PA06015255A MX PA06015255 A MXPA06015255 A MX PA06015255A MX PA06015255 A MXPA06015255 A MX PA06015255A
- Authority
- MX
- Mexico
- Prior art keywords
- plant
- variable data
- dependent variable
- operating
- dependent
- Prior art date
Links
- 238000000034 method Methods 0.000 title claims abstract description 43
- 230000001419 dependent effect Effects 0.000 claims abstract description 61
- 230000036962 time dependent Effects 0.000 claims abstract description 39
- 238000011156 evaluation Methods 0.000 claims abstract description 4
- 238000009795 derivation Methods 0.000 claims description 41
- 238000004088 simulation Methods 0.000 claims description 18
- 238000004364 calculation method Methods 0.000 claims description 15
- 230000033228 biological regulation Effects 0.000 claims description 13
- 229910052688 Gadolinium Inorganic materials 0.000 claims description 3
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 claims description 3
- 239000003758 nuclear fuel Substances 0.000 claims description 3
- 230000020169 heat generation Effects 0.000 claims description 2
- 230000008569 process Effects 0.000 description 14
- 238000013461 design Methods 0.000 description 12
- 239000000446 fuel Substances 0.000 description 10
- 230000009257 reactivity Effects 0.000 description 6
- 230000008859 change Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 238000012544 monitoring process Methods 0.000 description 3
- 238000012935 Averaging Methods 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 238000004891 communication Methods 0.000 description 2
- 238000013480 data collection Methods 0.000 description 2
- 238000001035 drying Methods 0.000 description 2
- 238000001914 filtration Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 241000590428 Panacea Species 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 230000003466 anti-cipated effect Effects 0.000 description 1
- 238000013528 artificial neural network Methods 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 238000005094 computer simulation Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000012937 correction Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000012552 review Methods 0.000 description 1
- 239000000725 suspension Substances 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
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
- G21D3/08—Regulation of any parameters in the plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| 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 |
|---|---|
| MXPA06015255A true MXPA06015255A (es) | 2008-10-17 |
Family
ID=37908123
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| MXPA06015255A MXPA06015255A (es) | 2005-12-30 | 2006-12-20 | Metodo para determinar imagenes para limites de operación para una operacion de reactor nuclear. |
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)
| 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)
| 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 |
-
2005
- 2005-12-30 US US11/320,919 patent/US7366273B2/en active Active
-
2006
- 2006-12-20 TW TW095147952A patent/TWI389138B/zh not_active IP Right Cessation
- 2006-12-20 MX MXPA06015255A patent/MXPA06015255A/es active IP Right Grant
- 2006-12-20 EP EP06126619A patent/EP1804255A3/en not_active Withdrawn
- 2006-12-27 JP JP2006350902A patent/JP5357389B2/ja active Active
- 2006-12-28 KR KR1020060136853A patent/KR20070072399A/ko not_active Withdrawn
- 2006-12-30 CN CNA2006100641326A patent/CN101034595A/zh active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| EP1804255A3 (en) | 2010-07-07 |
| US20070153958A1 (en) | 2007-07-05 |
| KR20070072399A (ko) | 2007-07-04 |
| 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 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| MXPA06015255A (es) | Metodo para determinar imagenes para limites de operación para una operacion de reactor nuclear. | |
| Bao et al. | A data-driven framework for error estimation and mesh-model optimization in system-level thermal-hydraulic simulation | |
| JP3704086B2 (ja) | 運転限界最小臨界出力比の評価方法、システムおよびプログラム | |
| CN112597631A (zh) | 轴向功率偏差的超实时计算方法、电子设备及存储介质 | |
| JP2007206060A (ja) | 制約問題に対する提案される解のロバストネスを評価し、制約問題の解を展開する際にロバストネスを考慮する方法および装置 | |
| Kavaklioglu et al. | Monitoring feedwater flow rate and component thermal performance of pressurized water reactors by means of artificial neural networks | |
| Sanchez-Saez et al. | Uncertainty analysis of PKL SBLOCA G7. 1 test simulation using TRACE with Wilks and GAM surrogate methods | |
| JP2014229283A (ja) | 設計計算結果補正装置および設計計算結果補正方法 | |
| Naghedolfeizi | Dynamic modeling of a pressurized water reactor plant for diagnostics and control | |
| Petruzzi | The casualidad method for uncertainty evaluation of best-estimate system thermal-hydraulic calculations | |
| JP5377420B2 (ja) | 誤差推定装置および誤差推定プログラム | |
| Szilard et al. | Industry application emergency core cooling system cladding acceptance criteria early demonstration | |
| JP2013020386A (ja) | 品質評価装置および品質評価方法 | |
| Casamor et al. | Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison | |
| JP2011106970A (ja) | 誤差推定装置および誤差推定プログラム | |
| Lee et al. | Prediction of DNBR using fuzzy support vector regression and uncertainty analysis | |
| CN112069441A (zh) | 一种堆芯瞬态三维功率分布在线重构方法 | |
| Liu et al. | Parameter Optimization of Steam Generator Water Level Control System Based on Piecewise ARX Modeling | |
| Ndum et al. | Sensitivity Analysis and Uncertainty Quantification of a Digital Twin-Based Simulator for Small Modular and Microreactors | |
| Abdullah et al. | TRIGA PUSPATI reactor: Model analysis and accuracy | |
| Bae et al. | Estimation of the power peaking factor in a nuclear reactor using support vector machines and uncertainty analysis | |
| Liao et al. | Applying machine learning to improve boa analysis of cips/cilc | |
| KR102891370B1 (ko) | 설명 가능한 인공지능 기반 핵비등이탈 정지 제한치 예측 시스템 | |
| Tylee | Bond graph modeling of nuclear reactor dynamics.[PWR] | |
| Mician et al. | Assessing the Phebus FPT-1 experiment: Insights from MELCOR 2.2 and ASYST codes |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| FG | Grant or registration |