ES8501560A1 - "sistema de inyeccion para suministrar agua a traves de un tubo de retorno de la vasija de presion de un sistema nuclear". - Google Patents

"sistema de inyeccion para suministrar agua a traves de un tubo de retorno de la vasija de presion de un sistema nuclear".

Info

Publication number
ES8501560A1
ES8501560A1 ES515516A ES515516A ES8501560A1 ES 8501560 A1 ES8501560 A1 ES 8501560A1 ES 515516 A ES515516 A ES 515516A ES 515516 A ES515516 A ES 515516A ES 8501560 A1 ES8501560 A1 ES 8501560A1
Authority
ES
Spain
Prior art keywords
water injection
steam
water
driven water
steam driven
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
ES515516A
Other languages
English (en)
Other versions
ES515516A0 (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.)
General Electric Co
Original Assignee
General Electric 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 General Electric Co filed Critical General Electric Co
Publication of ES8501560A1 publication Critical patent/ES8501560A1/es
Publication of ES515516A0 publication Critical patent/ES515516A0/es
Granted legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • G21C9/012—Pressure suppression by thermal accumulation or by steam condensation, e.g. ice condensers
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Nozzles (AREA)
  • Water Treatment By Electricity Or Magnetism (AREA)

Abstract

METODO Y APARATO PARA LA INYECCION EN ETAPAS MULTIPLES DE AGUA EN LA VASIJA A PRESION DE UN REACTOR NUCLEAR.EL METODO COMPRENDE LAS SIGUIENTES OPERACIONES: PRIMERA, SE ELEVA EL NIVEL DE PRESION DEL AGUA PROCEDENTE DE UNA FUENTE DE AGUA EN UN PRIMER INYECTOR ACCIONADO POR VAPOR PROCEDENTE DE LA VASIJA DE PRESION DEL REACTOR; SEGUNDA, SE ENFRIA EL AGUA QUE SALE DE DICHO PRIMER INYECTOR; TERCERA, SE ELEVA EL NIVEL DE PRESION DEL AGUA PROCEDENTE DE LA FUENTE, EN UNA BOMBA DE CHORRO ACCIONADA POR UNA PRIMERA PORCION DEL AGUA ENFRIADA PROCEDENTE DEL PRIMER INYECTOR; CUARTA, SE ELEVA EL NIVEL DE PRESION DE LA PORCION RESTANTE DE AGUA ENFRIADA EN UN SEGUNDO INYECTOR ACCIONADO POR VAPOR; Y POR ULTIMO, SE DIRIGE EL AGUA QUE SALE DEL SEGUNDO INYECTOR A TRAVES DEL TUBO DE RETORNO HACIA LA VASIJA DE PRESION.
ES515516A 1981-10-13 1982-09-06 "sistema de inyeccion para suministrar agua a traves de un tubo de retorno de la vasija de presion de un sistema nuclear". Granted ES515516A0 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/310,928 US4440719A (en) 1981-10-13 1981-10-13 Steam driven water injection

Publications (2)

Publication Number Publication Date
ES8501560A1 true ES8501560A1 (es) 1984-11-16
ES515516A0 ES515516A0 (es) 1984-11-16

Family

ID=23204654

Family Applications (1)

Application Number Title Priority Date Filing Date
ES515516A Granted ES515516A0 (es) 1981-10-13 1982-09-06 "sistema de inyeccion para suministrar agua a traves de un tubo de retorno de la vasija de presion de un sistema nuclear".

Country Status (6)

Country Link
US (1) US4440719A (es)
JP (1) JPS5895295A (es)
DE (1) DE3236778A1 (es)
ES (1) ES515516A0 (es)
IT (1) IT1154518B (es)
SE (1) SE455352B (es)

Families Citing this family (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4687626A (en) * 1985-01-18 1987-08-18 Tong Long S Passive safety device for emergency steam dump and heat removal for steam generators in nuclear power reactors
KR880010431A (ko) * 1987-02-04 1988-10-08 미다 가쓰시게 원자로 플랜트
US4767594A (en) * 1987-05-19 1988-08-30 General Electric Company Control of reactor coolant flow path during reactor decay heat removal
US4847043A (en) * 1988-01-25 1989-07-11 General Electric Company Steam-assisted jet pump
DE3814860C2 (de) * 1988-05-02 1994-09-08 Siemens Ag Siedewasser-Kernreaktor mit Natur-Umlauf
EP0514914B1 (en) * 1991-05-22 1997-09-03 Kabushiki Kaisha Toshiba Steam injector system
IT1263612B (it) * 1993-02-19 1996-08-27 Cise Spa Iniettore a vapore per alte pressioni
US5398267A (en) * 1993-10-12 1995-03-14 Reinsch; Arnold O. W. Passive decay heat removal and internal depressurization system for nuclear reactors
DE69422402T2 (de) * 1994-04-13 2000-08-03 Finmeccanica Spa Naturumlauf-Dampfkondensator für -Kernreaktorschutzsystemen
FR2746484B1 (fr) * 1996-03-25 1998-04-24 Commissariat Energie Atomique Dispositif d'alimentation en eau sous pression de la source d'eau d'un injecteur a vapeur
RU2124147C1 (ru) * 1997-10-29 1998-12-27 Попов Сергей Анатольевич Способ работы насосно-эжекторной установки и установка для его осуществления
JP4834349B2 (ja) * 2005-08-18 2011-12-14 株式会社東芝 原子炉格納容器冷却設備
JP5006178B2 (ja) * 2007-12-21 2012-08-22 株式会社東芝 原子炉格納容器およびそれを用いた原子力プラント
US9460818B2 (en) * 2012-03-21 2016-10-04 Ge-Hitachi Nuclear Energy Americas Llc Low pressure reactor safety systems and methods
JP5853054B2 (ja) * 2013-06-19 2016-02-09 コリア アトミック エナジー リサーチ インスティチュート 原子炉格納構造物の冷却システム

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US165843A (en) * 1875-07-20 Improvement in injectors
US270937A (en) * 1883-01-23 John desmond
US88620A (en) * 1869-04-06 Improvement in steam-pumps
US334597A (en) * 1886-01-19 Steam-jet pump
US234157A (en) * 1880-11-09 Emil wohlers
US272463A (en) * 1883-02-20 norwood
US722696A (en) * 1902-08-18 1903-03-17 Walter W Green Boiler-feed attachment.
US1777239A (en) * 1927-12-09 1930-09-30 G & J Weir Ltd Ejector in series
US1810873A (en) * 1929-05-16 1931-06-16 G & J Weir Ltd Multistage steam-jet ejector
US2852922A (en) * 1953-07-30 1958-09-23 Rheem Mfg Co Jet pump
US2808195A (en) * 1954-03-29 1957-10-01 Schutte & Koerting Co Steam jet vacuum pump system
US3380649A (en) * 1965-10-19 1968-04-30 Gen Electric Reactor pumping system
US3431168A (en) * 1967-06-26 1969-03-04 Gen Electric Reactor cooling system
US3575807A (en) * 1968-01-29 1971-04-20 Gen Electric Steam cooled reactor operation
US4051892A (en) * 1974-12-16 1977-10-04 Arnold Otto Winfried Reinsch Heat dissipation system
US4280796A (en) * 1976-05-10 1981-07-28 Reinsch Arnold O W Flash jet coolant circulation system

Also Published As

Publication number Publication date
DE3236778A1 (de) 1983-04-21
SE8204950D0 (sv) 1982-08-30
US4440719A (en) 1984-04-03
ES515516A0 (es) 1984-11-16
SE8204950L (sv) 1983-04-14
JPH0231837B2 (es) 1990-07-17
IT1154518B (it) 1987-01-21
IT8223090A0 (it) 1982-09-01
JPS5895295A (ja) 1983-06-06
SE455352B (sv) 1988-07-04

Similar Documents

Publication Publication Date Title
ES8501560A1 (es) "sistema de inyeccion para suministrar agua a traves de un tubo de retorno de la vasija de presion de un sistema nuclear".
SE8500900D0 (sv) Method for operating boiling water-type atomic power plant
SE417259B (sv) Forfarande for utstreckning av driften av ett kernkraftverks tryckvattenreaktor utover slutet av reaktorns normala brenslecykel
FR2476369B1 (fr) Procede de regulation de la puissance fournie par un reacteur nucleaire a eau sous pression a une turbine a vapeur
JPS541786A (en) Fuel exchanging method for boiling water reactor
GB1285677A (en) Nuclear reactor installations
JPS5437951A (en) Manufacturing method of water boiler heat exchanger
FR2295536A2 (fr) Dispositif autonome d'evacuation de la chaleur residuelle dans un reacteur a neutrons rapides refroidi au sodium
FR2540575B1 (fr) Dispositif de raccordement etanche d'un element plongeur a une enceinte, notamment pour raccorder des elements plongeurs chauffants au pressuriseur d'une centrale nucleaire a eau pressurisee
JPS53352A (en) Combined plant
GB1232767A (es)
GB949608A (en) Method for producing controlled circulation of water in a steam generator, and a steam generator employing the method
JPS5341604A (en) Feed water degassing apparatus in steam power generation and nuclear power generation
JPS5217145A (en) Process and device for recovering power using waste heat of condenser of power plant
JPS5420292A (en) Water feeding device and method of reactor
JPS53143801A (en) Steam generator
JPS5298345A (en) Heat storage water tank
JPS5423233A (en) Solar heat collector
JPS5395493A (en) Thermal output of reactor monitor
JPS5371358A (en) Automatic feeding hot water pot
JPS5741542A (en) Storage tank for use in solar heat utilizing system
JPS548213A (en) Steam condenser
JPS53146052A (en) Power plant with low boiling point medium turbine
JPS53125593A (en) Fast breeder producer plant
JPS52144592A (en) Control rods driving water tube in reactor

Legal Events

Date Code Title Description
MM4A Patent lapsed

Effective date: 19960506