ES2086761T3 - Sistema de evacuacion de calor residual del lado secundario para reactores nucleares de agua a presion. - Google Patents

Sistema de evacuacion de calor residual del lado secundario para reactores nucleares de agua a presion.

Info

Publication number
ES2086761T3
ES2086761T3 ES92916943T ES92916943T ES2086761T3 ES 2086761 T3 ES2086761 T3 ES 2086761T3 ES 92916943 T ES92916943 T ES 92916943T ES 92916943 T ES92916943 T ES 92916943T ES 2086761 T3 ES2086761 T3 ES 2086761T3
Authority
ES
Spain
Prior art keywords
secondary side
residual heat
supply water
steam generator
steam
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
ES92916943T
Other languages
English (en)
Inventor
Pramod Batheja
Otto Gremm
Werner Leidemann
Jurgen Wirkner
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.)
Siemens AG
Siemens Corp
Original Assignee
Siemens AG
Siemens Corp
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 Siemens AG, Siemens Corp filed Critical Siemens AG
Application granted granted Critical
Publication of ES2086761T3 publication Critical patent/ES2086761T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • 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
    • 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)

Abstract

UN SISTEMA PARA EVACUAR EL CALOR RESIDUAL EN EL LADO SECUNDARIO DE UN REACTOR DE AGUA A PRESION (R), ES EMPLEADO PARA ELIMINAR EL CALOR RESIDUAL A TRAVES DEL LADO SECUNDARIO DE UN GENERADOR DE VAPOR (D1) EN CIERTAS SITUACIONES DE OPERACION Y DE EMERGENCIA. PARA ESTE FIN EL GENERADOR DE VAPOR (D1) TIENE UNA CONEXION (D1-D2, D3) EN EL LADO DE VAPOR FRESCO Y DE AGUA DE ALIMENTACION HASTA EL LADO SECUNDARIO DE UN CONDENSADOR DE SEGURIDAD (SK1), PARA LO CUAL LA CONEXION EN EL LADO DE AGUA DE ALIMENTACION (D3) SE CONDUCE A LA UNION DE ALIMENTACION (S) DE UNA VALVULA CON CAMARA EN TORBELLINO (WV), CUYA UNION DE CONTROL (C) ESTA UNIDA CON UNA PARTE DE LA TUBERIA DE AGUA DE ALIMENTACION (D51) HACIA ABAJO DE LA CORRIENTE DE LA BOMBA DE AGUA DE ALIMENTACION PRINCIPAL (P2) Y SU SALIDA (E) DESEMBOCA EN LA CAMARA DE ENTRADA DE AGUA DE ALIMENTACION (C2) DEL GENERADOR DE VAPOR (D1). EL LADO TERCIARIO DEL CONDENSADOR DE SEGURIDAD (SK1) SE ALIMENTA DESDE UN RECIPIENTE (B) CON RESERVA DE AGUA DISPUESTO GEODESICAMENTE MAS ALTO; EL VAPOR GENERADO ES DESCARGADO A LA ATMOSFERA POR MEDIO DE UNA TUBERIA DE DESCARGA (B2), EN CASO NECESARIO CON DISPOSITIVO SEPARADOR. A CAUSA DE LA DISPOSICION GEODESICAMENTE MAS ALTA DEL CONDENSADOR DE SEGURIDAD (SK1) RESPECTO AL GENERADOR DE VAPOR (D1), SE REALIZA EL TRANSPORTE DE ENERGIA EN EL LADO SECUNDARIO POR CIRCULACION NATURAL.
ES92916943T 1991-08-12 1992-08-11 Sistema de evacuacion de calor residual del lado secundario para reactores nucleares de agua a presion. Expired - Lifetime ES2086761T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE4126630A DE4126630A1 (de) 1991-08-12 1991-08-12 Sekundaerseitiges nachwaermeabfuhrsystem fuer druckwasser-kernreaktoren

Publications (1)

Publication Number Publication Date
ES2086761T3 true ES2086761T3 (es) 1996-07-01

Family

ID=6438146

Family Applications (1)

Application Number Title Priority Date Filing Date
ES92916943T Expired - Lifetime ES2086761T3 (es) 1991-08-12 1992-08-11 Sistema de evacuacion de calor residual del lado secundario para reactores nucleares de agua a presion.

Country Status (5)

Country Link
US (1) US5414743A (es)
EP (1) EP0598779B1 (es)
DE (2) DE4126630A1 (es)
ES (1) ES2086761T3 (es)
WO (1) WO1993004481A1 (es)

Families Citing this family (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100189168B1 (ko) * 1995-12-01 1999-06-01 윤덕용 원자로의 피동 격납용기 냉각장치
US7251939B2 (en) * 2004-04-12 2007-08-07 Weldon Eugene Walker General method for disposal of produced water
US7757715B2 (en) * 2006-11-28 2010-07-20 Mitsubishi Heavy Industries, Ltd. Accumulator and method of manufacturing flow damper
US7881421B2 (en) 2006-11-28 2011-02-01 Mitsubishi Heavy Industries, Ltd. Accumulator
DE102010031610A1 (de) * 2010-07-21 2012-01-26 Areva Np Gmbh Komponente zum Führen oder Aufnehmen eines Fluids und Verfahren zum Überprüfen der Komponente
CN102163469B (zh) * 2011-02-14 2014-04-30 中国核电工程有限公司 一种核电站非能动专设安全系统
US20130044851A1 (en) * 2011-08-17 2013-02-21 Westinghouse Electric Company Llc Backup nuclear reactor auxiliary power using decay heat
FR2985841B1 (fr) * 2012-01-18 2014-02-21 Technicatome Systeme d'evacuation de la puissance residuelle d'un reacteur nucleaire a eau sous pression
FR2985842B1 (fr) * 2012-01-18 2014-02-21 Technicatome Systeme pour evacuer la puissance residuelle d'un reacteur nucleaire a eau sous pression
US9536629B2 (en) * 2012-07-24 2017-01-03 Westinghouse Electric Company Llc Passive power production during a nuclear station blackout
CN103632737A (zh) * 2012-08-20 2014-03-12 中国核动力研究设计院 一种核电站蒸汽发生器二次侧非能动余热排出系统
CN102867548A (zh) * 2012-09-27 2013-01-09 中国核电工程有限公司 一种能动与非能动相结合的二次侧堆芯热量导出装置
RU2595640C2 (ru) * 2014-12-04 2016-08-27 Акционерное общество "Научно-исследовательский и проектно-конструкторский институт энергетических технологий "АТОМПРОЕКТ" ("АО "АТОМПРОЕКТ") Система пассивного отвода тепла от водоводяного энергетического реактора через парогенератор
GB2568692B (en) * 2017-11-23 2020-01-22 Rolls Royce Plc Nuclear power plants
RU2697652C1 (ru) * 2018-09-28 2019-08-16 Акционерное Общество "Научно-Исследовательский И Проектно-Конструкторский Институт Энергетических Технологий "Атомпроект" Способ и система приведения атомной электростанции в безопасное состояние после экстремального воздействия
FR3090083B1 (fr) * 2018-12-13 2020-12-04 Commissariat A L Energie Atomique Et Aux Energies Alternatives Condenseur de secours pour générateur de vapeur
CN120344802A (zh) 2022-12-12 2025-07-18 法玛通股份有限公司 安全冷凝器和包含该安全冷凝器的核反应堆

Family Cites Families (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2459150C3 (de) * 1974-12-14 1988-07-07 BBC Brown Boveri AG, 6800 Mannheim Verfahren und Schaltungsanordnung zur Abfuhr der Nachzerfalls-Wärme eines Druckwasser-Reaktors im Störfall
DE2712444C3 (de) * 1977-03-22 1980-10-30 Institut Fuer Wasserbau Universitaet Stuttgart, 7000 Stuttgart Wirbelkammerventil
DE2712443C3 (de) * 1977-03-22 1981-08-20 Brombach, Hansjörg, Dr.-Ing., 6990 Bad Mergentheim Wirbelkammereinrichtung
DE2809466C3 (de) * 1978-03-04 1986-05-28 Brown Boveri Reaktor GmbH, 6800 Mannheim Einrichtung zur Notkühlung eines Dampferzeugers eines Kernkraftwerkes
SU910067A1 (ru) * 1980-10-10 1982-11-07 Предприятие П/Я А-3513 Система аварийного расхолаживани водоохлаждаемого реактора
SU971015A1 (ru) * 1981-03-04 1984-06-30 Предприятие П/Я Г-4285 Система аварийного охлаждени активной зоны водо-вод ного реактора
GB2104710A (en) * 1981-08-25 1983-03-09 Westinghouse Electric Corp Standby heat removal system for a nuclear reactor using flow diodes
FR2584228B1 (fr) * 1985-07-01 1987-12-24 Framatome Sa Dispositif de refroidissement de secours a surete intrinseque d'un reacteur nucleaire a eau sous pression.
EP0362596B1 (de) * 1988-09-30 1993-12-01 Siemens Aktiengesellschaft Heizreaktorsystem mit einer Nachwärmeabfuhr-Schaltung und Verwendung letzterer für Siedewasser- und Druckwasser-Kernreaktoren

Also Published As

Publication number Publication date
DE4126630A1 (de) 1993-02-18
EP0598779B1 (de) 1996-05-01
WO1993004481A1 (de) 1993-03-04
EP0598779A1 (de) 1994-06-01
US5414743A (en) 1995-05-09
DE59206192D1 (de) 1996-06-05

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