ES2031164T3 - Procedimiento para la determinacion del umbral de alarma de la relacion de calentamiento critico y dispositivo de realizacion de este procedimiento. - Google Patents

Procedimiento para la determinacion del umbral de alarma de la relacion de calentamiento critico y dispositivo de realizacion de este procedimiento.

Info

Publication number
ES2031164T3
ES2031164T3 ES198888101234T ES88101234T ES2031164T3 ES 2031164 T3 ES2031164 T3 ES 2031164T3 ES 198888101234 T ES198888101234 T ES 198888101234T ES 88101234 T ES88101234 T ES 88101234T ES 2031164 T3 ES2031164 T3 ES 2031164T3
Authority
ES
Spain
Prior art keywords
procedure
relation
determination
alarm threshold
carrying
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 - Lifetime
Application number
ES198888101234T
Other languages
English (en)
Inventor
Francois Foret
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Areva NP SAS
Original Assignee
Framatome SA
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Framatome SA filed Critical Framatome SA
Application granted granted Critical
Publication of ES2031164T3 publication Critical patent/ES2031164T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • 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
    • G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/36—Control circuits
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

LA DETERMINACION DE UN UMBRAL DE ALARMA BAJA (B) CON RELACION AL CALENTAMIENTO CRITICO DE UN REACTOR NUCLEAR SE HACE DE MANERA QUE LA POSICION DE LAS BARRAS QUE ASEGURAN LA REGULACION DE LA TEMPERATURA SEA ALTA, PERO EL VALOR DETERMINADO PARA ESTE UMBRAL SEA BAJO. EL INVENTO SE APLICA ESPECIALMENTE A LAS CENTRALES NUCLEARES DE AGUA PRESURIZADA UTILIZADAS PARA LA PRODUCCION DE ENERGIA ELECTRICA.
ES198888101234T 1987-01-30 1988-01-28 Procedimiento para la determinacion del umbral de alarma de la relacion de calentamiento critico y dispositivo de realizacion de este procedimiento. Expired - Lifetime ES2031164T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR8701162A FR2610446B1 (fr) 1987-01-30 1987-01-30 Procede de determination du seuil d'alarme du rapport d'echauffement critique, dispositif de mise en oeuvre, et procede de pilotage d'un reacteur nucleaire

Publications (1)

Publication Number Publication Date
ES2031164T3 true ES2031164T3 (es) 1992-12-01

Family

ID=9347449

Family Applications (1)

Application Number Title Priority Date Filing Date
ES198888101234T Expired - Lifetime ES2031164T3 (es) 1987-01-30 1988-01-28 Procedimiento para la determinacion del umbral de alarma de la relacion de calentamiento critico y dispositivo de realizacion de este procedimiento.

Country Status (8)

Country Link
US (1) US4836973A (es)
EP (1) EP0277594B1 (es)
JP (1) JPS63193090A (es)
KR (1) KR960013028B1 (es)
CN (1) CN1015680B (es)
DE (1) DE3869800D1 (es)
ES (1) ES2031164T3 (es)
FR (1) FR2610446B1 (es)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
FR2665013B1 (fr) * 1990-07-17 1992-09-18 Framatome Sa Procede de protection d'un reacteur nucleaire en cas d'elevation de sa charge.
CN104425047B (zh) * 2013-09-11 2018-08-21 中国广核集团有限公司 一种核电站中防止堆芯热功率超限值的方法
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

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3998693A (en) * 1970-11-23 1976-12-21 Combustion Engineering, Inc. Thermal margin control
US4318778A (en) * 1973-05-22 1982-03-09 Combustion Engineering, Inc. Method and apparatus for controlling a nuclear reactor
US4080251A (en) * 1973-05-22 1978-03-21 Combustion Engineering, Inc. Apparatus and method for controlling a nuclear reactor
US4330367A (en) * 1973-05-22 1982-05-18 Combustion Engineering, Inc. System and process for the control of a nuclear power system
US4075059A (en) * 1976-04-28 1978-02-21 Combustion Engineering, Inc. Reactor power reduction system and method
DE2735915C2 (de) * 1977-08-10 1983-01-20 Continental Gummi-Werke Ag, 3000 Hannover Fahrzeugluftreifen für einspurige Fahrzeuge
US4568513A (en) * 1982-07-26 1986-02-04 The Babcock & Wilcox Company Reactor power peaking information display
US4637911A (en) * 1984-07-24 1987-01-20 Massachusetts Institute Of Technology Apparatus and method for closed-loop control of reactor power
US4707324A (en) * 1984-12-27 1987-11-17 Westinghouse Electric Corp. Controlling the response of a pressurized water reactor to rapid fluctuations in load
US4699749A (en) * 1985-05-07 1987-10-13 Westinghouse Electric Corp. Controlling a nuclear reactor with dropped control rods
US4711753A (en) * 1986-03-19 1987-12-08 Westinghouse Electric Corp. Calibration of a nuclear reactor core parameter predictor
US4738818A (en) * 1986-09-29 1988-04-19 Westinghouse Electric Corp. Feedwater control in a PWR following reactor trip

Also Published As

Publication number Publication date
FR2610446B1 (fr) 1991-11-29
EP0277594A1 (fr) 1988-08-10
DE3869800D1 (de) 1992-05-14
FR2610446A1 (fr) 1988-08-05
EP0277594B1 (fr) 1992-04-08
US4836973A (en) 1989-06-06
CN1015680B (zh) 1992-02-26
KR880009385A (ko) 1988-09-15
JPS63193090A (ja) 1988-08-10
KR960013028B1 (ko) 1996-09-25
CN88101339A (zh) 1988-08-10

Similar Documents

Publication Publication Date Title
ES539976A0 (es) Procedimiento para convertir calor residual de energia electrica de un proceso industrial a temperatura elevada del tipo regenerativo.
DE69126787T2 (de) Kriechstromkontrolle für elektrochirurgischen generator
AU2002249497A1 (en) A nuclear power plant and a method of conditioning its power generation circuit
GB882689A (en) Improvements in or relating to nuclear reactors
ES2031164T3 (es) Procedimiento para la determinacion del umbral de alarma de la relacion de calentamiento critico y dispositivo de realizacion de este procedimiento.
SE7605981L (sv) Reglersystem for en kernkraftreaktor
AT361094B (de) Einrichtung zur notkuehlung der dampferzeugungs- anlage eines kernkraftwerkes
ES2079933T3 (es) Disposicion para la inertizacion pasiva de la mezcla de gases en la vasija de seguridad de una central nuclear.
DK102686D0 (da) Kombineret varmluftturbine-dampkraftanlaeg
SE7611716L (sv) Tryckhallningstank for tryckvattenreaktorer
BR8007706A (pt) Processo de elevacao de agua para geracao de energia e respectivos sistema gerador de energia e casa de forca
ES505992A0 (es) Procedimiento y su correspondiente dispositivo de almacenado de energia termica a baja temperatura.
SE7808302L (sv) Termodynamiskt forfarande for utnyttjande av hogtemperaturvermeenergi, serskilt for hojning av verkningsgraden hos ett vermekraftverk, samt vermekraftverk for genomforande av ett sadant forfarande
BR8406514A (pt) Caldeira de uma passagem e usina de energia de ciclo combinado
JPS52107402A (en) Water supply tank of thermal power plant
ES2069407T3 (es) Minicentral electrica hidraulica con turbina bulbo.
IT8133162V0 (it) Dispositivo atto alla regolazione del consumo energetico di apparecchiature che utilizzano energia elettrica per produrre riscaldamento (effetto joule)
ES2120844B1 (es) Central automatica para la recuperacion de energia termica mediante la captacion de temperaturas positivas y negativas.
RU1804653C (ru) Атомна станци
SU106876A1 (ru) Источник электрической энергии дл питани аварийной сети
JPS5351454A (en) Stabilized dc power source controller
JPS5354691A (en) Core cooling system of nuclear reactor
AR229752A1 (es) Disposicion para transformar la energia de las olas del mar en energia electrica
ITVE910058A1 (it) Diaterm
ES2074816T3 (es) Metodo y aparato para la separacion continua de residuos de suciedad de desechos metalicos.

Legal Events

Date Code Title Description
FG2A Definitive protection

Ref document number: 277594

Country of ref document: ES