ES8101805A1 - Sistema de seguridad para un reactor nuclear - Google Patents

Sistema de seguridad para un reactor nuclear

Info

Publication number
ES8101805A1
ES8101805A1 ES485030A ES485030A ES8101805A1 ES 8101805 A1 ES8101805 A1 ES 8101805A1 ES 485030 A ES485030 A ES 485030A ES 485030 A ES485030 A ES 485030A ES 8101805 A1 ES8101805 A1 ES 8101805A1
Authority
ES
Spain
Prior art keywords
phi
safety system
nuclear reactor
reactor
parameter
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
Application number
ES485030A
Other languages
English (en)
Other versions
ES485030A0 (es
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.)
Babcock and Wilcox Co
Original Assignee
Babcock and Wilcox Co
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 Babcock and Wilcox Co filed Critical Babcock and Wilcox Co
Publication of ES8101805A1 publication Critical patent/ES8101805A1/es
Publication of ES485030A0 publication Critical patent/ES485030A0/es
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/36Control circuits
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear 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)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Safety Devices In Control Systems (AREA)

Abstract

PROCEDIMIENTO DE VERIFICACION DE UN SISTEMA DE SEGURIDAD PARA UN REACTOR NUCLEAR. CONSISTE EN UTILIZAR UNA COMBINACION EN PARALELO DE MODULOS DE CALCULO, QUE RECIBEN CADA UNO LOS DATOS RELACIONADOS CON UN PARAMETRO PARTICULAR Y PRODUCEN A SU VEZ UNAS FUNCIONES QUE SE SUMAN CONJUNTAMENTE. CADA FUNCION INDIVIDUAL DEL GRUPO DE MODULOS EN PARALELO ESTA CONSTITUIDA, POR TANTO, POR UNA COMBINACION DE UN PARAMETRO UNICO Y DE UN GRUPO DE CONSTANTES, TRANSFORMANDOSE INDEPENDIENTEMENTE CADA PARAMETRO EN UNA FUNCION, DE TAL MANERA QUE SEA POSIBLE EFECTUAR UNA COMPROBACION ENTRE EL PARAMETRO Y LA SALIDA, UTILIZANDO TODOS LOS ESTADOS POSIBLES DEL CITADO PARAMETRO. POR TANTO, EL SISTEMA PUEDE SER VERIFICADO APLICANDO TODOS LOS VALORES POSIBLES DLE PARAMETRO A LA ENTRADA, CON EL FIN DE DETERMINAR QUE TODAS LAS FUNCIONES DE ESTE PARAMETRO, EN UNA SALIDA ANALOGICA, SON CORRESCTAS.
ES485030A 1979-01-22 1979-10-15 Sistema de seguridad para un reactor nuclear Granted ES485030A0 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/005,123 US4308099A (en) 1979-01-22 1979-01-22 Nuclear reactor safety system

Publications (2)

Publication Number Publication Date
ES8101805A1 true ES8101805A1 (es) 1980-12-16
ES485030A0 ES485030A0 (es) 1980-12-16

Family

ID=21714299

Family Applications (1)

Application Number Title Priority Date Filing Date
ES485030A Granted ES485030A0 (es) 1979-01-22 1979-10-15 Sistema de seguridad para un reactor nuclear

Country Status (10)

Country Link
US (1) US4308099A (es)
JP (1) JPS5599097A (es)
CA (1) CA1127778A (es)
CH (1) CH643673A5 (es)
DE (1) DE2929508C2 (es)
ES (1) ES485030A0 (es)
FR (1) FR2447080A1 (es)
GB (1) GB2040522B (es)
IT (1) IT1123844B (es)
MX (1) MX6481E (es)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2494877A1 (fr) * 1980-11-26 1982-05-28 Commissariat Energie Atomique Systeme logique de securite pour declencher l'action de protection d'un actionneur de surete
US4427620A (en) 1981-02-04 1984-01-24 Westinghouse Electric Corp. Nuclear reactor power supply
FR2518288A1 (fr) * 1981-12-11 1983-06-17 Commissariat Energie Atomique Dispositif de declenchement d'un actionneur de surete
GB2177832B (en) * 1985-07-01 1989-07-19 Charles Hoai Chi Method and apparatus for protecting press from being damaged by overload conditions
US5112565A (en) * 1990-01-03 1992-05-12 Ball Russell M Nuclear reactor multi-state digital control using digital topology
FR2665013B1 (fr) * 1990-07-17 1992-09-18 Framatome Sa Procede de protection d'un reacteur nucleaire en cas d'elevation de sa charge.
FR2665014B1 (fr) * 1990-07-17 1992-09-18 Framatome Sa Procede et dispositif de protection d'un reacteur nucleaire.

Family Cites Families (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE561894A (es) * 1956-10-26
US3202804A (en) * 1961-08-31 1965-08-24 North American Aviation Inc Method and apparatus for monitoring the operation of a system
US3423285A (en) * 1966-01-27 1969-01-21 Westinghouse Electric Corp Temperature control for a nuclear reactor
US3752735A (en) * 1970-07-16 1973-08-14 Combustion Eng Instrumentation for nuclear reactor core power measurements
JPS5122591B1 (es) * 1970-11-16 1976-07-10
US3778347A (en) * 1971-09-27 1973-12-11 Giras T Method and system for operating a boiling water reactor-steam turbine plant preferably under digital computer control
US4080251A (en) * 1973-05-22 1978-03-21 Combustion Engineering, Inc. Apparatus and method for controlling a nuclear reactor
FR2303355A1 (fr) * 1975-03-04 1976-10-01 Commissariat Energie Atomique Procede et dispositif de controle thermique du coeur d'un reacteur nucleaire
US4075059A (en) * 1976-04-28 1978-02-21 Combustion Engineering, Inc. Reactor power reduction system and method

Also Published As

Publication number Publication date
GB2040522A (en) 1980-08-28
CA1127778A (en) 1982-07-13
CH643673A5 (de) 1984-06-15
DE2929508C2 (de) 1984-07-19
DE2929508A1 (de) 1980-07-24
IT7926494A0 (it) 1979-10-15
FR2447080B1 (es) 1983-04-22
US4308099A (en) 1981-12-29
IT1123844B (it) 1986-04-30
GB2040522B (en) 1983-02-09
JPS5599097A (en) 1980-07-28
ES485030A0 (es) 1980-12-16
FR2447080A1 (fr) 1980-08-14
MX6481E (es) 1985-06-13

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