TW473737B - Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods - Google Patents
Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods Download PDFInfo
- Publication number
- TW473737B TW473737B TW089128431A TW89128431A TW473737B TW 473737 B TW473737 B TW 473737B TW 089128431 A TW089128431 A TW 089128431A TW 89128431 A TW89128431 A TW 89128431A TW 473737 B TW473737 B TW 473737B
- Authority
- TW
- Taiwan
- Prior art keywords
- fuel
- fuel rod
- reactor
- rod
- internal pressure
- Prior art date
Links
- 238000000034 method Methods 0.000 title claims abstract description 20
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 12
- 239000000446 fuel Substances 0.000 claims abstract description 115
- 238000004590 computer program Methods 0.000 claims abstract description 5
- 230000000930 thermomechanical effect Effects 0.000 claims description 24
- 238000004364 calculation method Methods 0.000 claims description 5
- 238000006243 chemical reaction Methods 0.000 claims description 5
- 238000013475 authorization Methods 0.000 claims 1
- 238000013500 data storage Methods 0.000 claims 1
- 238000013461 design Methods 0.000 abstract description 7
- 230000008569 process Effects 0.000 abstract description 3
- 238000012854 evaluation process Methods 0.000 abstract 2
- 238000005538 encapsulation Methods 0.000 description 5
- 239000000463 material Substances 0.000 description 3
- 239000008188 pellet Substances 0.000 description 3
- 238000012545 processing Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 230000001105 regulatory effect Effects 0.000 description 2
- 238000004088 simulation Methods 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000009471 action Effects 0.000 description 1
- 230000033228 biological regulation Effects 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000009472 formulation Methods 0.000 description 1
- 230000006870 function Effects 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 230000006911 nucleation Effects 0.000 description 1
- 238000010899 nucleation Methods 0.000 description 1
- 230000008520 organization Effects 0.000 description 1
- 239000006187 pill Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000011257 shell material Substances 0.000 description 1
- 238000010561 standard procedure Methods 0.000 description 1
- 238000001356 surgical procedure Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 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
-
- 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)
- General Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US17356199P | 1999-12-30 | 1999-12-30 | |
| US09/678,665 US6535568B1 (en) | 1999-12-30 | 2000-10-04 | Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| TW473737B true TW473737B (en) | 2002-01-21 |
Family
ID=26869287
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| TW089128431A TW473737B (en) | 1999-12-30 | 2000-12-30 | Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US6535568B1 (enExample) |
| EP (1) | EP1113455B1 (enExample) |
| JP (1) | JP4800477B2 (enExample) |
| ES (1) | ES2388600T3 (enExample) |
| TW (1) | TW473737B (enExample) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| TWI464748B (zh) * | 2007-09-26 | 2014-12-11 | Areva Np Inc | 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 |
Families Citing this family (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20030086520A1 (en) * | 2001-11-07 | 2003-05-08 | Russell William Earl | System and method for continuous optimization of control-variables during operation of a nuclear reactor |
| 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 |
| US9047995B2 (en) * | 2002-12-18 | 2015-06-02 | Global Nuclear Fuel—Americas, LLC | Method and system for designing a nuclear reactor core for uprated power operations |
| US8873698B2 (en) * | 2002-12-18 | 2014-10-28 | Global Nuclear Fuel—Americas, LLC | Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria |
| JP4600722B2 (ja) * | 2003-12-15 | 2010-12-15 | 株式会社グローバル・ニュークリア・フュエル・ジャパン | 炉心監視装置 |
| ES2429166T3 (es) * | 2005-08-31 | 2013-11-13 | Westinghouse Electric Sweden Ab | Procedimiento de estimación de las propiedades de desecación en un reactor nuclear de agua ligera |
| US7633531B2 (en) | 2006-12-31 | 2009-12-15 | General Electric Company | Systems and methods for quantitatively assessing the quality of an image produced by an imaging system |
| JP5388322B2 (ja) * | 2007-02-05 | 2014-01-15 | 原子燃料工業株式会社 | 燃料棒の健全性判定方法と判定手段 |
| FR2914103B1 (fr) * | 2007-03-19 | 2009-12-18 | Areva Np | Procede de determination de la distribution de puissance volumique du coeur d'un reacteur nucleaire |
| FR2924852B1 (fr) * | 2007-12-07 | 2010-02-19 | Areva Np | 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. |
| US9424376B2 (en) | 2011-11-18 | 2016-08-23 | Terrapower, Llc | Enhanced neutronics systems |
| EP3100274A4 (en) * | 2014-01-27 | 2017-08-30 | TerraPower LLC | Modeling for fuel element deformation |
| 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 |
| US10685754B2 (en) * | 2016-12-15 | 2020-06-16 | Westinghouse Electric Company Llc | Integration of real-time measurements and atomistic modeling to license nuclear components |
| CN112037950B (zh) * | 2020-09-24 | 2022-02-11 | 中国核动力研究设计院 | 一种燃料棒裂变产物释放模拟装置及其使用方法 |
| US20240304350A1 (en) * | 2021-06-25 | 2024-09-12 | Georgia Tech Research Corporation | Methods and systems for nuclear reactor design using fuel-cladding thermo-mechanics analysis |
| CN115455633A (zh) * | 2022-03-16 | 2022-12-09 | 广西防城港核电有限公司 | 一种核反应堆核燃料可靠性评估方法和系统 |
| JP7692386B2 (ja) * | 2022-04-19 | 2025-06-13 | 三菱重工業株式会社 | 冷却性能評価方法、解析装置、冷却性能評価プログラム |
Family Cites Families (14)
| 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 |
| JPS5938686A (ja) * | 1982-08-27 | 1984-03-02 | 株式会社日立製作所 | 原子炉出力制御装置 |
| JPS6060583A (ja) * | 1983-09-14 | 1985-04-08 | 株式会社日立製作所 | シヤツフリング燃料集合体選定方法 |
| JPS63108297A (ja) * | 1986-10-27 | 1988-05-13 | 株式会社東芝 | 原子炉炉心内の燃料健全性監視装置 |
| JP2868894B2 (ja) * | 1990-11-29 | 1999-03-10 | 株式会社東芝 | 原子力発電所の監視方法 |
| JP3064554B2 (ja) * | 1991-09-20 | 2000-07-12 | 株式会社日立製作所 | 原子炉の炉心特性監視装置 |
| JPH05323088A (ja) * | 1992-05-20 | 1993-12-07 | Toshiba Corp | 原子炉制御棒検査装置 |
| JP2807383B2 (ja) * | 1992-11-02 | 1998-10-08 | 株式会社東芝 | 運転制限値監視装置 |
| US6061412A (en) * | 1995-10-05 | 2000-05-09 | Westinghouse Electric Company Llc | Nuclear reaction protection system |
| 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 |
| US5991352A (en) * | 1998-03-30 | 1999-11-23 | General Electric Company | Method for determining corrosion susceptibility of nuclear fuel cladding to nodular corrosion |
| US6310929B1 (en) * | 1998-08-25 | 2001-10-30 | Kabushiki Kaisha Toshiba | In-core fixed nuclear instrumentation system and power distribution monitoring system |
| JP2000137093A (ja) * | 1998-08-25 | 2000-05-16 | Toshiba Corp | 原子炉の固定式炉内核計装システムおよび核計装処理方法、出力分布算出装置および算出方法、ならびに出力分布監視システムおよび監視方法 |
-
2000
- 2000-10-04 US US09/678,665 patent/US6535568B1/en not_active Expired - Lifetime
- 2000-12-22 ES ES00311650T patent/ES2388600T3/es not_active Expired - Lifetime
- 2000-12-22 EP EP00311650A patent/EP1113455B1/en not_active Expired - Lifetime
- 2000-12-28 JP JP2000399853A patent/JP4800477B2/ja not_active Expired - Lifetime
- 2000-12-30 TW TW089128431A patent/TW473737B/zh not_active IP Right Cessation
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| TWI464748B (zh) * | 2007-09-26 | 2014-12-11 | Areva Np Inc | 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| JP4800477B2 (ja) | 2011-10-26 |
| EP1113455A1 (en) | 2001-07-04 |
| ES2388600T3 (es) | 2012-10-16 |
| EP1113455B1 (en) | 2012-06-27 |
| US6535568B1 (en) | 2003-03-18 |
| JP2001296382A (ja) | 2001-10-26 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| TW473737B (en) | Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods | |
| TW513725B (en) | System and method for optimization of multiple operational control-variables for a nuclear reactor | |
| Allison et al. | Role of RELAP/SCDAPSIM in nuclear safety | |
| CN101939795A (zh) | 确定表征核反应堆的可操作性的参数值的方法、确定系统、计算机程序和相应的载体 | |
| Saghafi et al. | Determination of PAR configuration for PWR containment design: a hydrogen mitigation strategy | |
| Wang et al. | The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC | |
| Prošek et al. | The state-of-the-art theory and applications of best-estimate plus uncertainty methods | |
| Chen et al. | Uncertainty analysis of HPR-1000 LOCA with probabilistic and deterministic methods | |
| Malone et al. | Approach to startup inventory for viable commercial fusion power plant | |
| Lee et al. | Development of a coupled fuel (GIFT) and thermal (COBRA-SFS) analysis code for dry storage analysis and its application for the spent fuel safety analyses | |
| Yang et al. | Uncertainty and sensitivity analysis of in-vessel phenomena under severe accident mitigation strategy based on ISAA-SAUP program | |
| Bécares et al. | Review and comparison of effective delayed neutron fraction calculation methods with Monte Carlo codes | |
| Bielen et al. | NRC’s methodology to estimate fuel dispersal during a large break loss of coolant accident | |
| Prodea et al. | Bundle geometry design influence on fuel burnup and performances in a CANDU reactor | |
| Salman et al. | Nonlinear system dynamics simulation of thermal processes in the VVER-1200 reactor core | |
| Zoino et al. | Performance-based ECCS cladding acceptance criteria: A new simulation approach | |
| Huang et al. | A simplified approach to evaluating severe accident source term for PWR | |
| KR20210136395A (ko) | 몬테칼로법을 이용한 연료봉 성능 평가 방법 | |
| Booker et al. | A proposal and methodology for the accelerated implementation of probabilistic approaches in the nuclear sector | |
| Shah et al. | Concept design, application and optimization of operational parameters for new forced safety injection tank system | |
| Zhang et al. | An improved fuel design specification and evaluation process for Belgian nuclear power plants | |
| Novascone et al. | Demonstration of Coupled Tiamat Single Assembly Calculations | |
| Miller et al. | First Results for Uranium Nitride Fuel Characterization Using an Accelerated Fuel Qualification Process | |
| Al Hosani | BURST BEHAVIOUR OF ACCIDENT TOLERANT FUEL CLADDING MATERIALS | |
| Salko Jr et al. | Subchannel Methods Development for Modeling of Light Water Reactors at Oak Ridge National Laboratory |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GD4A | Issue of patent certificate for granted invention patent | ||
| MK4A | Expiration of patent term of an invention patent |