TWI389140B - 使用控制棒標準以降低急停時間的增進核反應器性能之方法 - Google Patents
使用控制棒標準以降低急停時間的增進核反應器性能之方法 Download PDFInfo
- Publication number
- TWI389140B TWI389140B TW095122995A TW95122995A TWI389140B TW I389140 B TWI389140 B TW I389140B TW 095122995 A TW095122995 A TW 095122995A TW 95122995 A TW95122995 A TW 95122995A TW I389140 B TWI389140 B TW I389140B
- Authority
- TW
- Taiwan
- Prior art keywords
- nuclear reactor
- control rod
- simulation
- core
- cpr
- Prior art date
Links
- 238000000034 method Methods 0.000 title claims description 37
- 238000004088 simulation Methods 0.000 claims description 31
- 238000003780 insertion Methods 0.000 claims description 20
- 230000037431 insertion Effects 0.000 claims description 20
- 230000002708 enhancing effect Effects 0.000 claims description 4
- 238000009835 boiling Methods 0.000 description 35
- 239000000446 fuel Substances 0.000 description 29
- 230000001052 transient effect Effects 0.000 description 23
- 238000009826 distribution Methods 0.000 description 21
- 230000029052 metamorphosis Effects 0.000 description 18
- 238000004364 calculation method Methods 0.000 description 13
- 230000008859 change Effects 0.000 description 9
- 238000012545 processing Methods 0.000 description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 9
- 238000010586 diagram Methods 0.000 description 8
- 238000011156 evaluation Methods 0.000 description 8
- 230000009257 reactivity Effects 0.000 description 8
- 230000033228 biological regulation Effects 0.000 description 6
- 238000013461 design Methods 0.000 description 6
- 230000000875 corresponding effect Effects 0.000 description 5
- 238000003860 storage Methods 0.000 description 4
- 238000006243 chemical reaction Methods 0.000 description 3
- 238000005315 distribution function Methods 0.000 description 3
- 238000012546 transfer Methods 0.000 description 3
- 238000000342 Monte Carlo simulation Methods 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 2
- 238000006073 displacement reaction Methods 0.000 description 2
- 230000033001 locomotion Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 230000001133 acceleration Effects 0.000 description 1
- 230000000172 allergic effect Effects 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 208000010668 atopic eczema Diseases 0.000 description 1
- 238000002680 cardiopulmonary resuscitation Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000002596 correlated effect Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000006870 function Effects 0.000 description 1
- 238000007429 general method Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 230000002503 metabolic effect Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 230000007261 regionalization Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 230000000452 restraining effect Effects 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 238000007619 statistical method Methods 0.000 description 1
Classifications
-
- 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
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
-
- 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)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US11/169,916 US7620139B2 (en) | 2005-06-30 | 2005-06-30 | Method of improving nuclear reactor performance during reactor core operation |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| TW200715304A TW200715304A (en) | 2007-04-16 |
| TWI389140B true TWI389140B (zh) | 2013-03-11 |
Family
ID=37103107
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| TW095122995A TWI389140B (zh) | 2005-06-30 | 2006-06-26 | 使用控制棒標準以降低急停時間的增進核反應器性能之方法 |
Country Status (7)
| Country | Link |
|---|---|
| US (1) | US7620139B2 (enExample) |
| EP (1) | EP1739684B1 (enExample) |
| JP (1) | JP5379344B2 (enExample) |
| CN (1) | CN1975936A (enExample) |
| ES (1) | ES2371771T3 (enExample) |
| MX (1) | MXPA06007604A (enExample) |
| TW (1) | TWI389140B (enExample) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8433029B2 (en) * | 2007-12-14 | 2013-04-30 | Global Nuclear Fuel—Americas, LLC | Determination of safety limit minimum critical power ratio |
| US7800382B2 (en) | 2007-12-19 | 2010-09-21 | AEHR Test Ststems | System for testing an integrated circuit of a device and its method of use |
| US8030957B2 (en) | 2009-03-25 | 2011-10-04 | Aehr Test Systems | System for testing an integrated circuit of a device and its method of use |
| CA2823960C (en) * | 2011-05-13 | 2014-08-05 | Neal MANN | Nuclear reactor control method and apparatus |
| KR101406849B1 (ko) * | 2012-12-27 | 2014-06-13 | 한국전력기술 주식회사 | 제어봉 삽입시간 측정을 위한 시뮬레이션 구축 방법 |
| US10593436B2 (en) * | 2013-11-21 | 2020-03-17 | Terrapower, Llc | Method and system for generating a nuclear reactor core loading distribution |
| CN110428919B (zh) * | 2019-07-08 | 2023-01-17 | 中国核电工程有限公司 | 基于征兆的压水堆核电厂反应性控制策略的设计方法 |
| CN112397211B (zh) * | 2020-11-18 | 2022-08-30 | 山东核电有限公司 | 一种任意控制棒位置下压水堆燃料相关组件配插分析方法 |
| CN119905281A (zh) * | 2024-12-05 | 2025-04-29 | 中广核研究院有限公司 | 核反应堆的处理方法、装置、设备、存储介质及产品 |
Family Cites Families (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4330367A (en) * | 1973-05-22 | 1982-05-18 | Combustion Engineering, Inc. | System and process for the control of a nuclear power system |
| BE838037A (fr) * | 1975-02-11 | 1976-05-14 | Commande de barre de reglage de reacteur nucleaire a la cuve sous pression | |
| US4075057A (en) * | 1975-03-21 | 1978-02-21 | Nasa | Non-equilibrium radiation nuclear reactor |
| JPS59211897A (ja) * | 1983-05-18 | 1984-11-30 | 株式会社日立製作所 | 制御棒スクラム時間測定装置 |
| JPH02257094A (ja) * | 1989-09-28 | 1990-10-17 | Toshiba Corp | 原子炉停止装置 |
| JPH03279898A (ja) * | 1990-03-28 | 1991-12-11 | Toshiba Corp | 原子炉出力制御装置 |
| JPH04265899A (ja) * | 1991-02-20 | 1992-09-22 | Hitachi Ltd | 原子炉シミュレータ |
| JP3156976B2 (ja) * | 1992-05-07 | 2001-04-16 | 株式会社東芝 | 制御棒駆動制御装置 |
| JPH08166487A (ja) * | 1994-12-15 | 1996-06-25 | Toshiba Syst Technol Kk | 運転計画装置 |
| JPH09101818A (ja) * | 1995-10-04 | 1997-04-15 | Toshiba Syst Technol Kk | 炉心性能監視システム |
| US5790616A (en) * | 1996-08-09 | 1998-08-04 | General Electric Company | Method and system for determining nuclear reactor core control blade positioning |
| JPH10142382A (ja) * | 1996-11-11 | 1998-05-29 | Hitachi Ltd | 原子炉炉心性能計算装置 |
| 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 |
| US6611572B2 (en) * | 2000-12-29 | 2003-08-26 | Global Nuclear Fuel - Americas, L.L.C. | Determination of operating limit minimum critical power ratio |
| JP2003130984A (ja) * | 2001-10-29 | 2003-05-08 | Global Nuclear Fuel-Japan Co Ltd | 原子炉の炉心性能監視装置 |
| US20040059549A1 (en) * | 2002-09-19 | 2004-03-25 | Kropaczek David Joseph | Method and apparatus for evaluating a proposed solution to a constraint problem |
| US6862329B1 (en) * | 2003-10-06 | 2005-03-01 | Global Nuclear Fuel-Americas Llc | In-cycle shuffle |
-
2005
- 2005-06-30 US US11/169,916 patent/US7620139B2/en not_active Expired - Lifetime
-
2006
- 2006-06-26 TW TW095122995A patent/TWI389140B/zh not_active IP Right Cessation
- 2006-06-28 JP JP2006177509A patent/JP5379344B2/ja not_active Expired - Fee Related
- 2006-06-29 EP EP06253390A patent/EP1739684B1/en not_active Not-in-force
- 2006-06-29 ES ES06253390T patent/ES2371771T3/es active Active
- 2006-06-30 CN CNA2006101719027A patent/CN1975936A/zh active Pending
- 2006-06-30 MX MXPA06007604A patent/MXPA06007604A/es active IP Right Grant
Also Published As
| Publication number | Publication date |
|---|---|
| JP5379344B2 (ja) | 2013-12-25 |
| CN1975936A (zh) | 2007-06-06 |
| EP1739684B1 (en) | 2011-10-05 |
| ES2371771T3 (es) | 2012-01-10 |
| TW200715304A (en) | 2007-04-16 |
| MXPA06007604A (es) | 2007-06-08 |
| US20070002997A1 (en) | 2007-01-04 |
| JP2007010661A (ja) | 2007-01-18 |
| EP1739684A1 (en) | 2007-01-03 |
| US7620139B2 (en) | 2009-11-17 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US6611572B2 (en) | Determination of operating limit minimum critical power ratio | |
| US5912933A (en) | Method and system for direct evaluation of operating limit minimum critical power ratios for boiling water reactors | |
| Queral et al. | AP1000® Large-Break LOCA BEPU analysis with TRACE code | |
| TWI464748B (zh) | 用於線上操縱的降階壓力模式、燃料破壞診斷以及輕水反應爐的爐心燃料佈局的設計 | |
| CN101086905B (zh) | 用于芯块-包壳交互作用分析的方法 | |
| TWI389140B (zh) | 使用控制棒標準以降低急停時間的增進核反應器性能之方法 | |
| Gorton et al. | Defining the performance envelope of reactivity-initiated accidents in a high-temperature gas-cooled reactor | |
| JP5947787B2 (ja) | バンドルおよび炉心の設計中および運転中における、ペレットクラッディング相互作用(pci)を評価および緩和するための方法 | |
| 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 | |
| JP5658432B2 (ja) | 原子燃料炉心のための安全限界最小限界出力比を決定するための方法 | |
| JP7117207B2 (ja) | 原子炉評価装置、原子炉評価装置方法及び原子炉評価プログラム | |
| JP5193477B2 (ja) | 原子炉の制御セルのセル摩擦測定基準を判定する方法 | |
| Lorenzi et al. | Spatial neutronics modelling to evaluate the temperature reactivity feedbacks in a lead-cooled fast reactor | |
| JP7788353B2 (ja) | 解析システム、解析方法及び解析プログラム | |
| Gamble | Mechanistic Multiphysics Modeling of Cladding Rupture in Nuclear Fuel Rods During Loss of Coolant Accident Conditions | |
| Matsumoto et al. | Advanced Safety Analysis Methodology-Development of New Core and Safety Analysis Codes | |
| Cunning et al. | An Examination of CANDU Fuel Performance Margins Derived from a Statistical Assessment of Industrial Manufacturing Data | |
| CN119315497A (zh) | 核电厂dnbr在线保护事故分析方法、装置、介质及设备 | |
| Villarino et al. | Thermal Hydraulic Models for Neutronic and Thermaly Hydraulic Feedback in CITVAP Code | |
| Yang et al. | Risk-informed time margin analysis for operators in main control room of nuclear power plant | |
| Scioscioli et al. | Multiphysics Analysis Of An In-Core Fission Product Removal System For The Molten Salt Fast Reactor | |
| Serbanel et al. | Coupled neutronic-thermalhydraulic simulation of Large LOCA for CANDU 6 NPP | |
| Kim et al. | Phase-B pre-simulation using boron and gadolinium as poison in the moderator system for Wolsong-1 | |
| Kotlyar et al. | Verification of coupled 3D fuel cycle analysis with stable Monte Carlo based code, BGCore, against the nodal diffusion DYN3D code | |
| Cunning et al. | A Statistical Assessment Of CANDU® Fuel Manufacturing Parameters And Their Impact On In-Reactor Performance During Transient Conditions |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| MM4A | Annulment or lapse of patent due to non-payment of fees |