JP5753383B2 - 原子炉の操作可能性を表すパラメータの値を決定する方法、決定システム、コンピュータプログラム及び対応する媒体 - Google Patents
原子炉の操作可能性を表すパラメータの値を決定する方法、決定システム、コンピュータプログラム及び対応する媒体 Download PDFInfo
- Publication number
- JP5753383B2 JP5753383B2 JP2010536506A JP2010536506A JP5753383B2 JP 5753383 B2 JP5753383 B2 JP 5753383B2 JP 2010536506 A JP2010536506 A JP 2010536506A JP 2010536506 A JP2010536506 A JP 2010536506A JP 5753383 B2 JP5753383 B2 JP 5753383B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- value
- steps
- operability
- core
- 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.)
- Expired - Fee Related
Links
- 238000000034 method Methods 0.000 title claims description 36
- 238000004590 computer program Methods 0.000 title claims description 4
- 239000000446 fuel Substances 0.000 claims description 37
- 238000000576 coating method Methods 0.000 claims description 29
- 239000003758 nuclear fuel Substances 0.000 claims description 29
- 239000011248 coating agent Substances 0.000 claims description 27
- 239000008188 pellet Substances 0.000 claims description 22
- 230000001052 transient effect Effects 0.000 claims description 20
- 238000004364 calculation method Methods 0.000 claims description 19
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 13
- 238000009826 distribution Methods 0.000 claims description 12
- 238000005253 cladding Methods 0.000 claims description 11
- 238000005259 measurement Methods 0.000 claims description 5
- 238000003860 storage Methods 0.000 claims description 4
- 230000000737 periodic effect Effects 0.000 claims description 2
- 238000001816 cooling Methods 0.000 description 16
- 238000012545 processing Methods 0.000 description 10
- 230000000712 assembly Effects 0.000 description 7
- 238000000429 assembly Methods 0.000 description 7
- 239000000498 cooling water Substances 0.000 description 7
- 230000007423 decrease Effects 0.000 description 5
- 230000004992 fission Effects 0.000 description 4
- 230000009257 reactivity Effects 0.000 description 4
- 241000006966 Areva Species 0.000 description 3
- 230000008859 change Effects 0.000 description 3
- 230000004907 flux Effects 0.000 description 3
- 230000006870 function Effects 0.000 description 3
- 239000000523 sample Substances 0.000 description 3
- 229910001093 Zr alloy Inorganic materials 0.000 description 2
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 2
- 238000013500 data storage Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000003780 insertion Methods 0.000 description 2
- 230000037431 insertion Effects 0.000 description 2
- 229910000439 uranium oxide Inorganic materials 0.000 description 2
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
- 239000011358 absorbing material Substances 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000001427 coherent effect Effects 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000001186 cumulative effect Effects 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000017525 heat dissipation Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 229910052740 iodine Inorganic materials 0.000 description 1
- 239000011630 iodine Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 230000015654 memory Effects 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 238000003303 reheating Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
Images
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
- G21D3/001—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)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR0759643A FR2924852B1 (fr) | 2007-12-07 | 2007-12-07 | 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. |
| FR0759643 | 2007-12-07 | ||
| PCT/FR2008/052104 WO2009071817A2 (fr) | 2007-12-07 | 2008-11-21 | Procede de determination de la valeur d'un parametre representatif de la manoeuvrabilite d'un reacteur nucleaire |
Publications (3)
| Publication Number | Publication Date |
|---|---|
| JP2011506920A JP2011506920A (ja) | 2011-03-03 |
| JP2011506920A5 JP2011506920A5 (enExample) | 2014-05-15 |
| JP5753383B2 true JP5753383B2 (ja) | 2015-07-22 |
Family
ID=39551652
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2010536506A Expired - Fee Related JP5753383B2 (ja) | 2007-12-07 | 2008-11-21 | 原子炉の操作可能性を表すパラメータの値を決定する方法、決定システム、コンピュータプログラム及び対応する媒体 |
Country Status (8)
| Country | Link |
|---|---|
| US (1) | US9997263B2 (enExample) |
| EP (1) | EP2218078B1 (enExample) |
| JP (1) | JP5753383B2 (enExample) |
| KR (1) | KR20100082804A (enExample) |
| CN (1) | CN101939795B (enExample) |
| FR (1) | FR2924852B1 (enExample) |
| WO (1) | WO2009071817A2 (enExample) |
| ZA (1) | ZA201003901B (enExample) |
Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2950466B1 (fr) * | 2009-09-22 | 2012-01-13 | Areva Np | Procede d'aide a l'exploitation d'un reacteur nucleaire. |
| CN105006262B (zh) * | 2015-06-15 | 2017-12-08 | 中广核研究院有限公司 | 一种标定核反应堆堆外探测器的方法 |
| 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 |
| FR3069694A1 (fr) * | 2017-07-28 | 2019-02-01 | Areva Np | Procede de surveillance d'un coeur nucleaire comprenant une relaxation d'un seuil, programme, support et reacteur nucleaire associes |
| FR3075449B1 (fr) | 2017-12-18 | 2020-01-10 | Areva Np | Procede de determination d'au moins une valeur limite d'au moins un parametre de fonctionnement d'un reacteur nucleaire, programme d'ordinateur et systeme electronique associes |
| FR3077412B1 (fr) | 2018-02-01 | 2021-07-23 | Framatome Sa | Procede de regulation de parametres operatoires d'un reacteur nucleaire et reacteur nucleaire correspondant |
| FR3085788B1 (fr) * | 2018-09-12 | 2020-11-27 | Framatome Sa | Procede de protection d'un reacteur nucleaire et reacteur nucleaire correspondant |
| JP7267189B2 (ja) * | 2019-12-20 | 2023-05-01 | 三菱重工業株式会社 | 出力制限値の解析方法、安全評価方法、炉心設計方法及び解析装置 |
| US20240186028A1 (en) * | 2021-04-29 | 2024-06-06 | Virginia Tech Intellectual Properties, Inc. | Testing and education microreactor |
| CN113408147B (zh) * | 2021-07-15 | 2022-07-05 | 中国科学院近代物理研究所 | 反应堆燃料性能分析计算方法、系统、存储介质及设备 |
| WO2023014241A1 (ru) * | 2021-08-05 | 2023-02-09 | Акционерное Общество "Российский Концерн По Производству Электрической И Тепловой Энергии На Атомных Станциях" | Способ корректировки погрешности показаний мощности ядерного реактора |
Family Cites Families (8)
| 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 |
| US4774049A (en) * | 1986-04-10 | 1988-09-27 | Westinghouse Electric Corp. | Two and three dimensional core power distribution monitor and display |
| US5091139A (en) * | 1989-06-26 | 1992-02-25 | General Electric Company | Automated thermal limit monitor |
| JP3871733B2 (ja) * | 1996-06-13 | 2007-01-24 | 株式会社東芝 | 原子炉の炉心監視装置 |
| US6535568B1 (en) * | 1999-12-30 | 2003-03-18 | Global Nuclear Fuel -- Americas Llc | Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods |
| US6611572B2 (en) * | 2000-12-29 | 2003-08-26 | Global Nuclear Fuel - Americas, L.L.C. | Determination of operating limit minimum critical power ratio |
| 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 |
| US8149983B2 (en) * | 2006-06-06 | 2012-04-03 | Westinghouse Electric Company Llc | Method for analysis of pellet-cladding interaction |
-
2007
- 2007-12-07 FR FR0759643A patent/FR2924852B1/fr not_active Expired - Fee Related
-
2008
- 2008-11-21 EP EP08857859.6A patent/EP2218078B1/fr active Active
- 2008-11-21 US US12/745,863 patent/US9997263B2/en not_active Expired - Fee Related
- 2008-11-21 WO PCT/FR2008/052104 patent/WO2009071817A2/fr not_active Ceased
- 2008-11-21 CN CN200880126186.8A patent/CN101939795B/zh active Active
- 2008-11-21 KR KR1020107012413A patent/KR20100082804A/ko not_active Ceased
- 2008-11-21 JP JP2010536506A patent/JP5753383B2/ja not_active Expired - Fee Related
-
2010
- 2010-06-01 ZA ZA2010/03901A patent/ZA201003901B/en unknown
Also Published As
| Publication number | Publication date |
|---|---|
| EP2218078A2 (fr) | 2010-08-18 |
| KR20100082804A (ko) | 2010-07-19 |
| WO2009071817A3 (fr) | 2009-08-13 |
| US20100260300A1 (en) | 2010-10-14 |
| ZA201003901B (en) | 2011-03-30 |
| CN101939795A (zh) | 2011-01-05 |
| FR2924852A1 (fr) | 2009-06-12 |
| JP2011506920A (ja) | 2011-03-03 |
| FR2924852B1 (fr) | 2010-02-19 |
| CN101939795B (zh) | 2014-01-22 |
| US9997263B2 (en) | 2018-06-12 |
| WO2009071817A2 (fr) | 2009-06-11 |
| EP2218078B1 (fr) | 2014-01-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP5753383B2 (ja) | 原子炉の操作可能性を表すパラメータの値を決定する方法、決定システム、コンピュータプログラム及び対応する媒体 | |
| 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 | |
| CN110970142B (zh) | 一种压水堆大破口失水事故始发应急工况预测方法 | |
| JP2011506920A5 (enExample) | ||
| CN109416947B (zh) | 用于计算与核反应堆的加载模式相关联的pci裕量的方法和系统 | |
| Pastore et al. | Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Fuel modeling developments and simulation of integral experiments | |
| Wang et al. | The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC | |
| CN112771625B (zh) | 用于保护核反应堆的方法和对应的核反应堆 | |
| JP7213886B2 (ja) | 原子炉の少なくとも1つの運転パラメータの少なくとも1つの閾値を決定するための方法、ならびに関連するコンピュータプログラムおよび電子システム | |
| Pilehvar et al. | Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor | |
| US20060129362A1 (en) | Method for determining threshold value of a nuclear reactor operating parameter, corresponding system, computer programme and support | |
| Jernkvist | Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik | |
| Jin et al. | Assessment of coated cladding impact on large-break LOCA with TRACE-DAKOTA | |
| JP7175960B2 (ja) | 閾値の緩和を含む核炉心を監視するための方法、および関連するプログラム、保持体、核原子炉 | |
| Manngård et al. | Evaluation of loss-of-coolant accident simulation tests with the fuel rod analysis code FRAPTRAN-1.4 | |
| Nawaz et al. | Comparative analysis of RIA and LOCA with and without fuel rod behavior modeling in THEATRe code | |
| Pelykh et al. | Theory of Fuel Life Control Methods at Nuclear Power Plants (NPP) with Water-Water Energetic Reactor (WWER) | |
| RU2772793C2 (ru) | Способ мониторинга активной зоны, включающий в себя ослабление порога, и соответствующие программа, носитель информации и ядерный реактор | |
| JP7788353B2 (ja) | 解析システム、解析方法及び解析プログラム | |
| Krasnaj | A Solid Element Approach to Analyzing CANDU Fuel Element Behaviour Under Post-Dryout Heat Transfer Conditions | |
| Kim | Dynamic Event Tree Analysis of Accident Tolerant Fuel Safety Benefits Considering Steam Generator Tube Degradation | |
| Wenqing et al. | Study and Application of Xenon Oscillation Control During PWR Pseudo Rod Ejection and Pseudo Rod Drop Tests | |
| Paraschiv et al. | Simulation of CANDU Fuel Behaviour into In-Reactor LOCA Tests | |
| Kima et al. | Development of cladding ballooning/burst model in FAMILY code based on creep model at high temperature | |
| PONCIROLI | Development of a model based approach for studying the system dynamics and control of Gen-IV lead-cooled fast reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A621 | Written request for application examination |
Free format text: JAPANESE INTERMEDIATE CODE: A621 Effective date: 20111014 |
|
| A131 | Notification of reasons for refusal |
Free format text: JAPANESE INTERMEDIATE CODE: A131 Effective date: 20130926 |
|
| A601 | Written request for extension of time |
Free format text: JAPANESE INTERMEDIATE CODE: A601 Effective date: 20131219 |
|
| A602 | Written permission of extension of time |
Free format text: JAPANESE INTERMEDIATE CODE: A602 Effective date: 20131227 |
|
| A524 | Written submission of copy of amendment under article 19 pct |
Free format text: JAPANESE INTERMEDIATE CODE: A524 Effective date: 20140326 |
|
| A521 | Request for written amendment filed |
Free format text: JAPANESE INTERMEDIATE CODE: A821 Effective date: 20140326 |
|
| A131 | Notification of reasons for refusal |
Free format text: JAPANESE INTERMEDIATE CODE: A131 Effective date: 20141006 |
|
| A601 | Written request for extension of time |
Free format text: JAPANESE INTERMEDIATE CODE: A601 Effective date: 20141219 |
|
| TRDD | Decision of grant or rejection written | ||
| A01 | Written decision to grant a patent or to grant a registration (utility model) |
Free format text: JAPANESE INTERMEDIATE CODE: A01 Effective date: 20150430 |
|
| A61 | First payment of annual fees (during grant procedure) |
Free format text: JAPANESE INTERMEDIATE CODE: A61 Effective date: 20150522 |
|
| R150 | Certificate of patent or registration of utility model |
Ref document number: 5753383 Country of ref document: JP Free format text: JAPANESE INTERMEDIATE CODE: R150 |
|
| R250 | Receipt of annual fees |
Free format text: JAPANESE INTERMEDIATE CODE: R250 |
|
| R250 | Receipt of annual fees |
Free format text: JAPANESE INTERMEDIATE CODE: R250 |
|
| R250 | Receipt of annual fees |
Free format text: JAPANESE INTERMEDIATE CODE: R250 |
|
| R250 | Receipt of annual fees |
Free format text: JAPANESE INTERMEDIATE CODE: R250 |
|
| LAPS | Cancellation because of no payment of annual fees |