ES466129A1 - Metodo de explotacion de un reactor nuclear para permitir elseguimiento de carga - Google Patents
Metodo de explotacion de un reactor nuclear para permitir elseguimiento de cargaInfo
- Publication number
- ES466129A1 ES466129A1 ES466129A ES466129A ES466129A1 ES 466129 A1 ES466129 A1 ES 466129A1 ES 466129 A ES466129 A ES 466129A ES 466129 A ES466129 A ES 466129A ES 466129 A1 ES466129 A1 ES 466129A1
- Authority
- ES
- Spain
- Prior art keywords
- core
- power distribution
- reactivity
- employed
- maintaining
- 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
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/12—Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
- G21D3/16—Varying reactivity
-
- 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
- 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)
Abstract
Método de explotación de un reactor nuclear para permitir el seguimiento de carga, teniendo el reactor un núcleo reactivo que incluye material fisionable con una dimensión axial, un medio refrigerante y un moderador, respectivamente para extraer el calor del núcleo y para frenar los neutrones de fisión en el núcleo, teniendo el moderador un coeficiente de temperatura de reactividad negativo, incluyendo el método la operación que consiste en mantener una distribución de potencia sustancialmente constante en sentido axial a través del núcleo, estando dicho método caracterizado porque la reactividad en el interior del núcleo se aumenta sin alterar sustancialmente la distribución axial de la potencia del núcleo, al producirse una demanda dada, mediante una reducción de la temperatura del refrigerante de una manera controlada.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US05/760,490 US4222822A (en) | 1977-01-19 | 1977-01-19 | Method for operating a nuclear reactor to accommodate load follow while maintaining a substantially constant axial power distribution |
Publications (1)
Publication Number | Publication Date |
---|---|
ES466129A1 true ES466129A1 (es) | 1979-02-01 |
Family
ID=25059257
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES466129A Expired ES466129A1 (es) | 1977-01-19 | 1978-01-18 | Metodo de explotacion de un reactor nuclear para permitir elseguimiento de carga |
Country Status (11)
Country | Link |
---|---|
US (1) | US4222822A (es) |
JP (1) | JPS59800B2 (es) |
BE (1) | BE863090A (es) |
CA (1) | CA1097441A (es) |
CH (1) | CH625362A5 (es) |
DE (1) | DE2800552A1 (es) |
ES (1) | ES466129A1 (es) |
FR (1) | FR2378335A1 (es) |
GB (1) | GB1544399A (es) |
IT (1) | IT1092108B (es) |
SE (1) | SE436810B (es) |
Families Citing this family (27)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2942013C2 (de) * | 1978-10-18 | 1984-10-18 | Hitachi, Ltd., Tokio/Tokyo | Verfahren und Anordnung zur Regelung eines Siedewasserreaktors |
JPS56163497A (en) * | 1980-05-21 | 1981-12-16 | Tokyo Shibaura Electric Co | Method and device for operating follow-up atomic power plant |
FR2493582A1 (fr) * | 1980-11-03 | 1982-05-07 | Framatome Sa | Procede de conduite d'un reacteur nucleaire par deplacement, dans le coeur de ce reacteur, de groupes de barres de commande |
US4582669A (en) * | 1982-01-08 | 1986-04-15 | Westinghouse Electric Corp. | Xenon suppression in a nuclear fueled electric power generation system |
GB2122409B (en) * | 1982-06-17 | 1985-10-16 | Westinghouse Electric Corp | Method for controlling a nuclear fueled electric power generating unit and interfacing the same with a load dispatching system |
FR2544907B1 (fr) * | 1983-04-21 | 1985-07-19 | Framatome Sa | Procede de reglage automatique de la teneur en bore soluble de l'eau de refroidissement d'un reacteur nucleaire a eau sous pression |
US4642213A (en) * | 1984-07-27 | 1987-02-10 | Westinghouse Electric Corp. | Anticipatory control of xenon in a pressurized water reactor |
US4759896A (en) * | 1984-10-31 | 1988-07-26 | Westinghouse Electric Corp. | Method and apparatus for improving flux reduction factors |
US4707324A (en) * | 1984-12-27 | 1987-11-17 | Westinghouse Electric Corp. | Controlling the response of a pressurized water reactor to rapid fluctuations in load |
FR2619950B1 (fr) * | 1987-08-24 | 1991-11-29 | Framatome Sa | Procede de protection d'un reacteur nucleaire a eau pressurisee contre les defaillances du dispositif d'arret d'urgence |
FR2629624B1 (fr) * | 1988-04-05 | 1990-11-16 | Framatome Sa | Procede de determination et d'evaluation de la capacite de retour en puissance d'un reacteur nucleaire a eau pressurisee |
FR2639141B1 (fr) * | 1988-11-14 | 1991-02-01 | Framatome Sa | Procede de pilotage de reacteur nucleaire a eau sous pression et reacteur nucleaire en faisant application |
FR2665014B1 (fr) * | 1990-07-17 | 1992-09-18 | Framatome Sa | Procede et dispositif de protection d'un reacteur nucleaire. |
WO2003025952A1 (en) * | 2001-09-14 | 2003-03-27 | Pebble Bed Modular Reactor (Proprietary) Limited | A method of operating a nuclear power plant and a nuclear power plant |
US7596198B1 (en) | 2005-04-01 | 2009-09-29 | Westinghouse Electric Co Llc | Over temperature and over power delta temperature operating margin recovery method and reactor system employing the same |
DE102005030485A1 (de) * | 2005-06-28 | 2007-01-04 | Framatome Anp Gmbh | Pumpenvorrichtung für kerntechnische Anlagen |
JP4585527B2 (ja) * | 2006-03-02 | 2010-11-24 | ウエスチングハウス・エレクトリック・カンパニー・エルエルシー | 原子炉システムのトリップ制御方法及び原子炉システム |
KR101119548B1 (ko) * | 2007-08-21 | 2012-03-13 | 미쯔비시 헤비 인더스트리즈 리미티드 | 축방향 출력분포 제어방법, 축방향 출력분포 제어시스템 및 축방향 출력분포 제어프로그램 |
US8953732B2 (en) * | 2010-12-09 | 2015-02-10 | Westinghouse Electric Company Llc | Nuclear reactor internal hydraulic control rod drive mechanism assembly |
US8699653B2 (en) * | 2011-10-24 | 2014-04-15 | Westinghouse Electric Company, Llc | Method of achieving automatic axial power distribution control |
FR2985363B1 (fr) * | 2011-12-29 | 2015-01-30 | Areva Np | Procede de pilotage d'un reacteur nucleaire a eau pressurisee |
JP2013192195A (ja) * | 2012-02-16 | 2013-09-26 | Denso Corp | 音響装置 |
FR3008220B1 (fr) * | 2013-07-04 | 2015-08-14 | Areva Np | Procede de pilotage en prolongation de cycle d'un reacteur nucleaire a eau pressurisee |
ES2945114T3 (es) * | 2019-05-07 | 2023-06-28 | Framatome Gmbh | Procedimiento de regulación de un reactor nuclear de agua a presión y sistema de regulación acorde |
CN111508620B (zh) * | 2020-04-30 | 2023-03-24 | 中国核动力研究设计院 | 一种反应堆机动性自调节方法 |
CN111724920A (zh) * | 2020-05-21 | 2020-09-29 | 岭东核电有限公司 | 核电站反应堆寿期末降功率的轴向功率偏差控制方法 |
CN118053606A (zh) * | 2020-05-22 | 2024-05-17 | 华龙国际核电技术有限公司 | 核电厂安全因素的确定方法及装置 |
Family Cites Families (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE568438A (es) * | 1957-06-12 | |||
US3070536A (en) * | 1958-08-29 | 1962-12-25 | Babcock & Wilcox Ltd | Plant including nuclear reactor |
NL244977A (es) * | 1958-11-04 | 1900-01-01 | ||
US3247069A (en) * | 1960-07-13 | 1966-04-19 | Combustion Eng | Control of nuclear power plant |
US3276965A (en) * | 1963-06-17 | 1966-10-04 | Internuclear Company | Single pass superheat reactor |
GB880489A (en) * | 1964-02-24 | 1961-10-25 | Atomic Energy Authority Uk | Improvements in or relating to nuclear reactors |
US3423285A (en) * | 1966-01-27 | 1969-01-21 | Westinghouse Electric Corp | Temperature control for a nuclear reactor |
US3630839A (en) * | 1968-11-26 | 1971-12-28 | Westinghouse Electric Corp | System and method for operating a boiling water reactor-steam turbine plant |
US3700552A (en) * | 1969-11-19 | 1972-10-24 | Babcock & Wilcox Co | Nuclear reactor with means for adjusting coolant temperature |
US3998693A (en) * | 1970-11-23 | 1976-12-21 | Combustion Engineering, Inc. | Thermal margin control |
US3799839A (en) * | 1971-01-07 | 1974-03-26 | Gen Electric | Reactivity and power distribution control of nuclear reactor |
US3920513A (en) * | 1973-04-18 | 1975-11-18 | Westinghouse Electric Corp | Protection system for a nuclear reactor |
US4000037A (en) * | 1973-11-28 | 1976-12-28 | Westinghouse Electric Corporation | Reactor-turbine control for low steam pressure operation in a pressurized water reactor |
US4057463A (en) * | 1974-08-29 | 1977-11-08 | Westinghouse Electric Corporation | Method of operating a nuclear reactor which maintains a substantially constant axial power distribution profile with changes in load |
-
1977
- 1977-01-19 US US05/760,490 patent/US4222822A/en not_active Expired - Lifetime
-
1978
- 1978-01-07 DE DE19782800552 patent/DE2800552A1/de not_active Withdrawn
- 1978-01-09 GB GB726/78A patent/GB1544399A/en not_active Expired
- 1978-01-16 CA CA294,975A patent/CA1097441A/en not_active Expired
- 1978-01-18 JP JP53003429A patent/JPS59800B2/ja not_active Expired
- 1978-01-18 IT IT19379/78A patent/IT1092108B/it active
- 1978-01-18 SE SE7800614A patent/SE436810B/sv not_active IP Right Cessation
- 1978-01-18 FR FR7801359A patent/FR2378335A1/fr active Granted
- 1978-01-18 ES ES466129A patent/ES466129A1/es not_active Expired
- 1978-01-18 CH CH51878A patent/CH625362A5/de not_active IP Right Cessation
- 1978-01-19 BE BE184461A patent/BE863090A/xx not_active IP Right Cessation
Also Published As
Publication number | Publication date |
---|---|
SE436810B (sv) | 1985-01-21 |
IT1092108B (it) | 1985-07-06 |
CH625362A5 (es) | 1981-09-15 |
JPS5390590A (en) | 1978-08-09 |
BE863090A (fr) | 1978-07-19 |
US4222822A (en) | 1980-09-16 |
JPS59800B2 (ja) | 1984-01-09 |
GB1544399A (en) | 1979-04-19 |
FR2378335B1 (es) | 1984-07-06 |
DE2800552A1 (de) | 1978-07-20 |
SE7800614L (sv) | 1978-07-20 |
CA1097441A (en) | 1981-03-10 |
FR2378335A1 (fr) | 1978-08-18 |
IT7819379A0 (it) | 1978-01-18 |
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