ES2401349T3 - Sistemas y procedimientos de predicción de una k efectiva crítica para un reactor nuclear - Google Patents
Sistemas y procedimientos de predicción de una k efectiva crítica para un reactor nuclear Download PDFInfo
- Publication number
- ES2401349T3 ES2401349T3 ES07121547T ES07121547T ES2401349T3 ES 2401349 T3 ES2401349 T3 ES 2401349T3 ES 07121547 T ES07121547 T ES 07121547T ES 07121547 T ES07121547 T ES 07121547T ES 2401349 T3 ES2401349 T3 ES 2401349T3
- Authority
- ES
- Spain
- Prior art keywords
- nominal
- effective
- change
- core
- power
- 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.)
- Active
Links
- 238000000034 method Methods 0.000 title claims abstract description 99
- 230000009257 reactivity Effects 0.000 claims abstract description 132
- 230000008859 change Effects 0.000 claims abstract description 116
- 229910052688 Gadolinium Inorganic materials 0.000 claims abstract description 61
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 claims abstract description 60
- 229910052724 xenon Inorganic materials 0.000 claims abstract description 56
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 claims abstract description 55
- 239000002826 coolant Substances 0.000 claims abstract description 17
- 239000013643 reference control Substances 0.000 claims abstract description 3
- 230000006870 function Effects 0.000 claims description 11
- 238000004364 calculation method Methods 0.000 claims description 9
- 230000007423 decrease Effects 0.000 claims description 6
- 230000004044 response Effects 0.000 claims description 4
- 238000013461 design Methods 0.000 description 13
- 238000004458 analytical method Methods 0.000 description 8
- 230000008569 process Effects 0.000 description 7
- 239000003507 refrigerant Substances 0.000 description 7
- 238000010606 normalization Methods 0.000 description 6
- 238000006243 chemical reaction Methods 0.000 description 5
- 230000000694 effects Effects 0.000 description 4
- 238000012545 processing Methods 0.000 description 4
- 238000003860 storage Methods 0.000 description 4
- 238000004891 communication Methods 0.000 description 3
- 230000001276 controlling effect Effects 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 238000005259 measurement Methods 0.000 description 3
- 238000012544 monitoring process Methods 0.000 description 3
- 238000004088 simulation Methods 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- 230000003287 optical effect Effects 0.000 description 2
- 238000005457 optimization Methods 0.000 description 2
- 230000001105 regulatory effect Effects 0.000 description 2
- 208000003569 Central serous chorioretinopathy Diseases 0.000 description 1
- 101000916644 Homo sapiens Macrophage colony-stimulating factor 1 receptor Proteins 0.000 description 1
- 102100028198 Macrophage colony-stimulating factor 1 receptor Human genes 0.000 description 1
- 239000011358 absorbing material Substances 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000012512 characterization method Methods 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000012938 design process Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 230000014509 gene expression Effects 0.000 description 1
- 229910052735 hafnium Inorganic materials 0.000 description 1
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 238000010348 incorporation Methods 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000004069 plant analysis Substances 0.000 description 1
- 239000004065 semiconductor Substances 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 230000001960 triggered effect Effects 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/36—Control circuits
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/14—Period meters
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US11/606,320 US7532698B2 (en) | 2006-11-29 | 2006-11-29 | Systems and methods of predicting a critical effective k for a nuclear reactor |
| US606320 | 2006-11-29 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| ES2401349T3 true ES2401349T3 (es) | 2013-04-18 |
Family
ID=38982446
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| ES07121547T Active ES2401349T3 (es) | 2006-11-29 | 2007-11-26 | Sistemas y procedimientos de predicción de una k efectiva crítica para un reactor nuclear |
Country Status (6)
| Country | Link |
|---|---|
| US (1) | US7532698B2 (enExample) |
| EP (1) | EP1927994B1 (enExample) |
| JP (1) | JP5634006B2 (enExample) |
| ES (1) | ES2401349T3 (enExample) |
| MX (1) | MX2007013918A (enExample) |
| TW (1) | TWI431638B (enExample) |
Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7966139B2 (en) * | 2008-01-23 | 2011-06-21 | Atomic Energy Council-Institute Of Nuclear Energy Research | Apparatus for monitoring the maintenance of systems in a nuclear power plant |
| EP2287855B1 (en) * | 2009-08-18 | 2012-10-03 | Areva NP | A computer implemented method for modelling a nuclear reactor core and a corresponding computer program product |
| US9793013B2 (en) * | 2009-11-06 | 2017-10-17 | Terrapower, Llc | Systems and methods for controlling reactivity in a nuclear fission reactor |
| US9190177B2 (en) * | 2009-11-06 | 2015-11-17 | Terrapower, Llc | Systems and methods for controlling reactivity in a nuclear fission reactor |
| US9852818B2 (en) * | 2009-11-06 | 2017-12-26 | Terrapower, Llc | Systems and methods for controlling reactivity in a nuclear fission reactor |
| CN102714065B (zh) * | 2009-11-06 | 2016-08-24 | 泰拉能源有限责任公司 | 用于控制核反应堆中的反应性的系统和方法 |
| US9748006B2 (en) * | 2010-10-01 | 2017-08-29 | Terrapower, Llc | System and method for maintaining and establishing operational readiness in a fuel cell backup system of a nuclear reactor system |
| US9691508B2 (en) | 2010-10-01 | 2017-06-27 | Terrapower, Llc | System and method for determining a state of operational readiness of a fuel cell backup system of a nuclear reactor system |
| RU2673564C1 (ru) * | 2018-04-18 | 2018-11-28 | Федеральное государственное бюджетное учреждение "Национальный исследовательский центр "Курчатовский институт" | Способ пуска ядерного реактора космического назначения |
| JP7192150B2 (ja) * | 2019-05-07 | 2022-12-19 | フラマトム・ゲーエムベーハー | 加圧水型原子炉の管理方法および応分の管理システム |
| CN113806941B (zh) * | 2021-09-22 | 2024-01-05 | 上海核星核电科技有限公司 | 一种具有氙瞬态模拟能力的压水堆燃耗跟踪计算方法 |
| CN114743700A (zh) * | 2022-04-19 | 2022-07-12 | 华能山东石岛湾核电有限公司 | 一种高温气冷堆多普勒发热点功率确定的方法 |
Family Cites Families (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5135890A (en) | 1974-09-20 | 1976-03-26 | Hitachi Ltd | Genshiro no jidokidoseigyosochi |
| US4515749A (en) | 1981-08-24 | 1985-05-07 | General Electric Company | Subcriticality measurement apparatus and method |
| US4588547A (en) | 1983-10-07 | 1986-05-13 | Westinghouse Electric Corp. | Method and apparatus for determining the nearness to criticality of a nuclear reactor |
| JPS61144595A (ja) * | 1984-12-18 | 1986-07-02 | 株式会社東芝 | プロセス計算機 |
| JPH07119827B2 (ja) | 1987-12-25 | 1995-12-20 | 三菱電機株式会社 | 原子炉出力分布の測定装置 |
| JP3792735B2 (ja) * | 1994-01-20 | 2006-07-05 | 株式会社東芝 | 沸騰水型原子炉用燃料集合体およびその炉心 |
| US5490184A (en) | 1994-07-21 | 1996-02-06 | Westinghouse Electric Corporation | Method and a system for accurately calculating PWR power from excore detector currents corrected for changes in 3-D power distribution and coolant density |
| US6061412A (en) | 1995-10-05 | 2000-05-09 | Westinghouse Electric Company Llc | Nuclear reaction protection system |
| US6314327B1 (en) | 1998-04-28 | 2001-11-06 | The University Of Akron | Method for predicting future function values utilizing derivative samples |
| JP4008131B2 (ja) * | 1998-11-26 | 2007-11-14 | 株式会社日立製作所 | 原子炉炉心性能計算装置 |
| US6181759B1 (en) | 1999-07-23 | 2001-01-30 | Westinghouse Electric Company Llc | Method and apparatus for determining nearness to criticality of a nuclear fueled electric power generating unit |
| US6801593B2 (en) | 2002-11-21 | 2004-10-05 | Westinghouse Electric Company Llc | Subcritical reactivity measurement method |
-
2006
- 2006-11-29 US US11/606,320 patent/US7532698B2/en active Active
-
2007
- 2007-11-07 MX MX2007013918A patent/MX2007013918A/es active IP Right Grant
- 2007-11-16 TW TW096143475A patent/TWI431638B/zh active
- 2007-11-26 JP JP2007303925A patent/JP5634006B2/ja active Active
- 2007-11-26 ES ES07121547T patent/ES2401349T3/es active Active
- 2007-11-26 EP EP07121547A patent/EP1927994B1/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| EP1927994A3 (en) | 2010-06-23 |
| US20080123794A1 (en) | 2008-05-29 |
| EP1927994B1 (en) | 2013-01-09 |
| TW200836217A (en) | 2008-09-01 |
| JP5634006B2 (ja) | 2014-12-03 |
| US7532698B2 (en) | 2009-05-12 |
| TWI431638B (zh) | 2014-03-21 |
| MX2007013918A (es) | 2009-02-19 |
| JP2008139308A (ja) | 2008-06-19 |
| EP1927994A2 (en) | 2008-06-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| ES2401349T3 (es) | Sistemas y procedimientos de predicción de una k efectiva crítica para un reactor nuclear | |
| EP1221701A1 (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 | |
| EP2613324A1 (en) | Critical heat flux prediction device, critical heat flux prediction method and safety evaluation system | |
| ES3022839T3 (en) | Method of providing bwr fuel pellets comprising determining u-235 enrichment levels determined by a computer-implemented simulation such that crud deposition does not occur under pre-determined boundary conditions | |
| CN101669176A (zh) | 确定核反应堆堆芯三维功率分布的方法 | |
| Mirvakili et al. | Developing a computational tool for predicting physical parameters of a typical VVER-1000 core based on artificial neural network | |
| EP2071581A2 (en) | Method and apparatus for determination of safety limit minimum critical power ratio for a nuclear fuel core | |
| Chatzidakis et al. | Evaluation of RELAP5/MOD3 behavior against loss of flow experimental results from two research reactor facilities | |
| JP2007183268A (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 | |
| CN112509716B (zh) | 基于信息融合理论的反应堆三维功率概率分布监测方法 | |
| Ramuhalli et al. | Uncertainty quantification techniques for sensor calibration monitoring in nuclear power plants | |
| Cadini et al. | Passive systems failure probability estimation by the meta-AK-IS2 algorithm | |
| Stakhanova et al. | Application of the MOCABA algorithm and the FSTC tool for source term predictions during severe accident scenarios | |
| ES2429166T3 (es) | Procedimiento de estimación de las propiedades de desecación en un reactor nuclear de agua ligera | |
| Keller et al. | Nonparametric estimation of the probability of detection of flaws in an industrial component, from destructive and nondestructive testing data, using approximate Bayesian computation | |
| EP1739684B1 (en) | Method of reducing scram time of a nuclear reactor | |
| Zedler et al. | Experimental study of the influence of cross-overflow on the decay heat removal from spent fuel pools | |
| Prieto | Experimental Characterization of HTGR Reactor Cavity Gas Dynamics Following a Primary System Rupture | |
| Bajs et al. | Development of the qualified plant nodalization for safety and operational transient analysis | |
| Mishra et al. | Selection of fuel channels for Thermal Power Measurement in 700 MWe Indian PHWR by evolutionary algorithm | |
| Riva et al. | FEniCSx-OpenMC Coupling for Neutronic Calculation with Temperature Feedback | |
| Pun-Quach et al. | A BEPU analysis separating epistemic and aleatory errors to compute accurate dryout power uncertainties | |
| Grishchenko et al. | Sensitivity study of steam explosion characteristics to uncertain input parameters using TEXAS-V code | |
| Umbehaun et al. | Brazil's Benchmark Results against Experimental Data from IEA-R1 |