DE3571889D1 - Method and apparatus for continuous on-line monitoring of power distribution in a nuclear reactor core - Google Patents
Method and apparatus for continuous on-line monitoring of power distribution in a nuclear reactor coreInfo
- Publication number
- DE3571889D1 DE3571889D1 DE8585300268T DE3571889T DE3571889D1 DE 3571889 D1 DE3571889 D1 DE 3571889D1 DE 8585300268 T DE8585300268 T DE 8585300268T DE 3571889 T DE3571889 T DE 3571889T DE 3571889 D1 DE3571889 D1 DE 3571889D1
- Authority
- DE
- Germany
- Prior art keywords
- continuous
- power distribution
- nuclear reactor
- line monitoring
- reactor 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
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US06/572,499 US4637910A (en) | 1984-01-20 | 1984-01-20 | Method and apparatus for continuous on-line synthesis of power distribution in a nuclear reactor core |
Publications (1)
Publication Number | Publication Date |
---|---|
DE3571889D1 true DE3571889D1 (en) | 1989-08-31 |
Family
ID=24288089
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DE8585300268T Expired DE3571889D1 (en) | 1984-01-20 | 1985-01-15 | Method and apparatus for continuous on-line monitoring of power distribution in a nuclear reactor core |
Country Status (7)
Country | Link |
---|---|
US (1) | US4637910A (de) |
EP (1) | EP0150096B1 (de) |
JP (1) | JPS60162994A (de) |
KR (1) | KR910008358B1 (de) |
DE (1) | DE3571889D1 (de) |
ES (1) | ES8900030A1 (de) |
GB (1) | GB2153522B (de) |
Families Citing this family (35)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4671919A (en) * | 1985-08-23 | 1987-06-09 | Westinghouse Electric Corp. | Reactor power level monitoring system using an alpha-beta tracker |
US4711753A (en) * | 1986-03-19 | 1987-12-08 | Westinghouse Electric Corp. | Calibration of a nuclear reactor core parameter predictor |
US4737917A (en) * | 1986-07-15 | 1988-04-12 | Emhart Industries, Inc. | Method and apparatus for generating isotherms in a forehearth temperature control system |
US4770843A (en) * | 1987-04-08 | 1988-09-13 | Westinghouse Electric Corp. | Controlling fuel assembly stability in a boiling water reactor |
FR2614461B1 (fr) * | 1987-04-24 | 1989-06-09 | Commissariat Energie Atomique | Procede de controle d'un reacteur nucleaire |
US4839134A (en) * | 1987-12-31 | 1989-06-13 | Westinghouse Electric Corp. | Continuous, online nuclear power distribution synthesis system and method |
US4877575A (en) * | 1988-01-19 | 1989-10-31 | Westinghouse Electric Corp. | Core reactivity validation computer and method |
US4927594A (en) * | 1988-08-10 | 1990-05-22 | Westinghouse Electric Corp. | Thermocouple based control rod position indication system |
US5024801A (en) * | 1989-05-01 | 1991-06-18 | Westinghouse Electric Corp. | Reactor core model update system |
US5091139A (en) * | 1989-06-26 | 1992-02-25 | General Electric Company | Automated thermal limit monitor |
US5174946A (en) * | 1991-01-22 | 1992-12-29 | General Electric Company | Oscillation power monitoring system and method for nuclear reactors |
US5229066A (en) * | 1991-08-05 | 1993-07-20 | Westinghouse Electric Corp. | Control rod position indication system |
US5108694A (en) * | 1991-08-23 | 1992-04-28 | Westinghouse Electric Corp. | Power distribution measuring system employing gamma detectors outside of nuclear reactor vessel |
US5251242A (en) * | 1992-06-22 | 1993-10-05 | Westinghouse Electric Corp. | Bi-metallic, self powered, fixed incore detector, and method of calibrating same |
US5297174A (en) * | 1993-05-26 | 1994-03-22 | Westinghouse Electric Corp. | Safety system grade apparatus and method for detecting a dropped control rod and malfunctioning exit thermocouples in a pressurized water reactor |
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 |
US5555279A (en) * | 1994-11-16 | 1996-09-10 | Nir; Israel | System for monitoring and controlling nuclear reactors |
US6061412A (en) * | 1995-10-05 | 2000-05-09 | Westinghouse Electric Company Llc | Nuclear reaction protection system |
US5790616A (en) * | 1996-08-09 | 1998-08-04 | General Electric Company | Method and system for determining nuclear reactor core control blade positioning |
US6353650B1 (en) * | 1997-12-22 | 2002-03-05 | Westinghouse Electric Company Llc | Reduced in-core instrument patterns for pressurized water reactors |
FR2796196B1 (fr) * | 1999-07-05 | 2001-10-19 | Framatome Sa | Procede et dispositif de surveillance d'au moins un parametre de fonctionnement du coeur d'un reacteur nucleaire |
FR2796197B1 (fr) * | 1999-07-05 | 2001-10-12 | Framatome Sa | Procede et dispositif de surveillance d'au moins un parametre de fonctionnement du coeur d'un reacteur nucleaire |
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 |
US6636577B1 (en) * | 2002-06-21 | 2003-10-21 | General Electric Company | Laser induced fluorescence water measurement system for nuclear reactors |
US20060165209A1 (en) * | 2005-01-27 | 2006-07-27 | Cheng Alexander Y | Neutron detector assembly with variable length rhodium emitters |
US8445839B2 (en) * | 2010-10-14 | 2013-05-21 | Areva Np Inc. | Self-calibrating, highly accurate, long-lived, dual rhodium vanadium emitter nuclear in-core detector |
FR2996695B1 (fr) * | 2012-10-09 | 2016-04-01 | Electricite De France | Centrale de pilotage d'une batterie de stockage d'energie |
KR101651893B1 (ko) * | 2015-04-13 | 2016-08-29 | 한전원자력연료 주식회사 | 신경망 회로를 이용한 원자로 노심의 축방향 출력분포 합성방법 및 그 방법이 적용된 노심감시계통 |
CN106782687B (zh) * | 2015-11-20 | 2023-11-28 | 国家电投集团科学技术研究院有限公司 | 装载193盒燃料组件的堆芯的探测器布置方法 |
CN106782688B (zh) * | 2015-11-20 | 2024-01-05 | 国家电投集团科学技术研究院有限公司 | 装载157盒燃料组件的堆芯的探测器布置方法 |
WO2018131106A1 (ja) * | 2017-01-12 | 2018-07-19 | 日立Geニュークリア・エナジー株式会社 | 制御棒動作監視システム及び制御棒動作監視方法 |
CN111799006B (zh) * | 2020-06-05 | 2021-11-09 | 江苏核电有限公司 | 一种中子温度测量通道软硬件连接正确性的检查方法 |
CN112133462B (zh) * | 2020-09-24 | 2022-07-29 | 中国核动力研究设计院 | 一种临界装置功率刻度方法 |
CN113409975B (zh) * | 2021-06-17 | 2022-11-15 | 中国核动力研究设计院 | 基于模型降阶和数据同化的堆芯功率分布监测方法及系统 |
CN115862912B (zh) * | 2023-02-27 | 2023-05-02 | 西安交通大学 | 一种动态氙条件下压水堆堆芯功率分布测量方法 |
Family Cites Families (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3565760A (en) * | 1967-10-23 | 1971-02-23 | Gen Electric | Nuclear reactor power monitor system |
US4318778A (en) * | 1973-05-22 | 1982-03-09 | Combustion Engineering, Inc. | Method and apparatus for controlling a nuclear reactor |
DE2337354C3 (de) * | 1973-07-23 | 1981-06-25 | Siemens AG, 1000 Berlin und 8000 München | Vorrichtung zur Regelung eines Druckwasserreaktors mit verstellbaren Steuerstäben |
DE2346725A1 (de) * | 1973-09-17 | 1975-03-27 | Siemens Ag | Kernreaktor |
JPS5142895A (en) * | 1974-10-11 | 1976-04-12 | Hitachi Ltd | Genshiroseigyokeino koshohanbetsusochi |
US4075059A (en) * | 1976-04-28 | 1978-02-21 | Combustion Engineering, Inc. | Reactor power reduction system and method |
DE2653411A1 (de) * | 1976-11-24 | 1978-06-01 | Kraftwerk Union Ag | Kernreaktor und verfahren zur ermittlung der leistungsverteilung im reaktorkern |
US4432930A (en) * | 1980-12-16 | 1984-02-21 | Westinghouse Electric Corp. | Spectral shift reactor control method |
-
1984
- 1984-01-20 US US06/572,499 patent/US4637910A/en not_active Expired - Fee Related
-
1985
- 1985-01-14 ES ES539544A patent/ES8900030A1/es not_active Expired
- 1985-01-15 GB GB08500929A patent/GB2153522B/en not_active Expired
- 1985-01-15 EP EP85300268A patent/EP0150096B1/de not_active Expired
- 1985-01-15 DE DE8585300268T patent/DE3571889D1/de not_active Expired
- 1985-01-19 KR KR1019850000321A patent/KR910008358B1/ko active IP Right Grant
- 1985-01-21 JP JP60007655A patent/JPS60162994A/ja active Granted
Also Published As
Publication number | Publication date |
---|---|
JPH0511596B2 (de) | 1993-02-15 |
GB2153522B (en) | 1987-12-16 |
GB2153522A (en) | 1985-08-21 |
EP0150096A3 (en) | 1987-09-23 |
EP0150096A2 (de) | 1985-07-31 |
GB8500929D0 (en) | 1985-03-27 |
ES539544A0 (es) | 1988-11-01 |
JPS60162994A (ja) | 1985-08-24 |
US4637910A (en) | 1987-01-20 |
KR850005712A (ko) | 1985-08-28 |
ES8900030A1 (es) | 1988-11-01 |
EP0150096B1 (de) | 1989-07-26 |
KR910008358B1 (ko) | 1991-10-12 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
8364 | No opposition during term of opposition | ||
8339 | Ceased/non-payment of the annual fee |