ES2108224T3 - Mitigacion de las rupturas de tubos de generadores de vapor en un reactor de agua presurizada con sistemas pasivos de seguridad. - Google Patents

Mitigacion de las rupturas de tubos de generadores de vapor en un reactor de agua presurizada con sistemas pasivos de seguridad.

Info

Publication number
ES2108224T3
ES2108224T3 ES93304675T ES93304675T ES2108224T3 ES 2108224 T3 ES2108224 T3 ES 2108224T3 ES 93304675 T ES93304675 T ES 93304675T ES 93304675 T ES93304675 T ES 93304675T ES 2108224 T3 ES2108224 T3 ES 2108224T3
Authority
ES
Spain
Prior art keywords
steam generator
reactor
ruptures
mitigation
water reactor
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
ES93304675T
Other languages
English (en)
Inventor
Daniel Joseph Mcdermott
Terry Lee Schulz
Kenneth Joseph Schrader
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.)
Westinghouse Electric Corp
Original Assignee
Westinghouse Electric 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 Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Application granted granted Critical
Publication of ES2108224T3 publication Critical patent/ES2108224T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • 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
    • 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)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

LOS EFECTOS DE LAS RUPTURAS DE TUBOS DE GENERADOR DE VAPOR (21) EN UN REACTOR DE AGUA A PRESION (1) SE MITIGAN REDUCIENDO LA PRESION EN UN BUCLE PRIMARIO DESVIANDO FLUIDO REFRIGERANTE DE REACTOR A TRAVES DEL INTERCAMBIADOR DE CALOR (37) DE UN SISTEMA DE ELIMINACION DE CALOR PASIVO SUMERGIDO EN UN TANQUE DE ALMACENAMIENTO DE AGUA DE RELLENO DE CONTENCION (35) EN RESPUESTA A UN NIVEL DE AGUA DE ALIMENTACION ALTO EN EL GENERADOR DE VAPOR (11). EL INVENTARIO DE FLUIDO REFRIGERANTE DE REACTOR SE MANTIENE TAMBIEN EN RESPUESTA AL NIVEL ALTO DE GENERADOR DE VAPOR PRODUCIENDO FLUIDO REFRIGERANTE DENTRO DEL PRIMER BUCLE A PARTIR DEL TANQUE DE RELLENO DEL NUCLEO (43) A LA PRESION EN EL PRESURIZADOR DEL SISTEMA DE FLUIDO REFRIGERANTE DEL REACTOR (31) EL NIVEL ALTO DEL GENERADOR DE VAPOR SE UTILIZA TAMBIEN PARA AISLAR EL SISTEMA DE AGUA DE ALIMENTACION DE ACTIVACION (81) Y EL SISTEMA DE CONTROL DE VOLUMEN Y QUIMICO (85) PARA EVITAR INUNDACIONES DENTRO DEL COLECTOR DE VAPOR.
ES93304675T 1992-06-24 1993-06-16 Mitigacion de las rupturas de tubos de generadores de vapor en un reactor de agua presurizada con sistemas pasivos de seguridad. Expired - Lifetime ES2108224T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US07/903,683 US5309487A (en) 1992-06-24 1992-06-24 Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems

Publications (1)

Publication Number Publication Date
ES2108224T3 true ES2108224T3 (es) 1997-12-16

Family

ID=25417917

Family Applications (1)

Application Number Title Priority Date Filing Date
ES93304675T Expired - Lifetime ES2108224T3 (es) 1992-06-24 1993-06-16 Mitigacion de las rupturas de tubos de generadores de vapor en un reactor de agua presurizada con sistemas pasivos de seguridad.

Country Status (8)

Country Link
US (1) US5309487A (es)
EP (1) EP0578392B1 (es)
JP (1) JP3194818B2 (es)
KR (1) KR100300889B1 (es)
CN (1) CN1041569C (es)
CZ (1) CZ283278B6 (es)
DE (1) DE69313046T2 (es)
ES (1) ES2108224T3 (es)

Families Citing this family (34)

* 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
FR2729459A1 (fr) * 1995-01-18 1996-07-19 Commissariat Energie Atomique Dispositif de vaporisation du melange diphasique d'un circuit de refroidissement en cas de procedure de depressurisation
FR2748844B1 (fr) * 1996-05-17 1998-08-14 Framatome Sa Dispositif de recuperation de fluide contenu dans le circuit de refroidissement d'un reacteur nucleaire
US5828714A (en) * 1996-12-19 1998-10-27 Westinghouse Electric Corporation Enhanced passive safety system for a nuclear pressurized water reactor
DE19752668A1 (de) * 1997-11-27 1999-06-02 Siemens Ag Vorrichtung zur Zufuhr eines neutronenabsorbierenden Fluides in den Primärkreislauf eines Druckwasserreaktors und Verfahren zur Erhöhung der Neutronenabsorption in einem solchen Primärkreislauf
FR2800504B1 (fr) * 1999-11-02 2002-04-05 Framatome Sa Procede et dispositif d'injection d'une solution aqueuse renfermant un element absorbeur de neutrons dans une canalisation d'un circuit primaire d'un reacteur nucleaire refroidi par de l'eau sous pression
US9984777B2 (en) * 2007-11-15 2018-05-29 Nuscale Power, Llc Passive emergency feedwater system
US8588360B2 (en) 2007-11-15 2013-11-19 The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University Evacuated containment vessel for a nuclear reactor
US8437446B2 (en) 2008-11-17 2013-05-07 Nuscale Power, Llc Steam generator flow by-pass system
CN102637464A (zh) * 2012-03-30 2012-08-15 中国核电工程有限公司 双层混凝土安全壳非能动热量导出系统强化换热方法及装置
CN103871505A (zh) * 2012-12-11 2014-06-18 中国核动力研究设计院 一种核电厂蒸汽排放系统自动快速冷却方法
CN103871531B (zh) * 2012-12-11 2016-08-31 中国核动力研究设计院 一种事故工况下延长蒸汽发生器满溢时间的方法
US9383095B2 (en) 2013-09-18 2016-07-05 Skavis Corporation Steam generation apparatus and associated control system and methods for providing desired steam quality
US9310070B2 (en) * 2013-09-18 2016-04-12 Skavis Corporation Steam generation apparatus and associated control system and methods for providing venting
US9303865B2 (en) 2013-09-18 2016-04-05 Skavis Corporation Steam generation apparatus and associated control system and methods for startup
US9303866B2 (en) 2013-09-18 2016-04-05 Skavis Corporation Steam generation apparatus and associated control system and methods for providing a desired injection pressure
US10529458B2 (en) 2014-07-22 2020-01-07 Bwxt Mpower, Inc. Integral isolation valve systems for loss of coolant accident protection
CN104112482B (zh) * 2014-07-30 2016-09-28 中广核研究院有限公司 非能动自流量控制注水系统
FR3030862B1 (fr) * 2014-12-17 2017-01-27 Dcns Procede de gestion de l'arret d'un reacteur nucleaire a eau pressurisee
CN104733060A (zh) * 2015-03-25 2015-06-24 东南大学 一种船用核动力装置的非能动余热排出系统
DE102016207832B4 (de) * 2016-05-06 2018-04-05 Areva Gmbh Passives Füllstandsregelsystem
RU2646859C2 (ru) * 2016-08-15 2018-03-12 Акционерное общество "Опытное Конструкторское Бюро Машиностроения имени И.И. Африкантова" (АО "ОКБМ Африкантов") Система аварийного отвода тепла
RU2668235C1 (ru) * 2017-12-07 2018-09-27 Российская Федерация, от имени которой выступает ФОНД ПЕРСПЕКТИВНЫХ ИССЛЕДОВАНИЙ Система аварийного расхолаживания
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
CN109859866B (zh) * 2019-03-06 2022-02-22 中国核动力研究设计院 一种缓解主蒸汽管道破裂事故后果的方法
CN109994230B (zh) * 2019-04-12 2024-11-15 西安热工研究院有限公司 一种核电站蒸汽发生器非能动事故排放与冷却方法
CN110148480B (zh) * 2019-05-28 2021-01-12 中广核研究院有限公司 一种核电二回路系统
CN110689973B (zh) * 2019-09-18 2023-04-28 上海电力大学 一种传热管破裂事故下核电站一回路降压控制方法
KR102348091B1 (ko) * 2020-04-01 2022-01-10 한국원자력연구원 증기 발생기 사고 대처 시스템
RU2740641C1 (ru) * 2020-06-10 2021-01-19 Федеральное государственное казенное военное образовательное учреждение высшего образования "Военный учебно-научный центр Военно-Морского Флота "Военно-морская академия им. Адмирала Флота Советского Союза Н.Г. Кузнецова" Многопозиционное устройство экстренного снижения мощности ядерного реактора
CN111681794B (zh) * 2020-06-19 2022-02-22 中国核动力研究设计院 一种压水堆核电厂全范围sgtr事故处理方法及系统
KR102504841B1 (ko) * 2021-04-06 2023-02-28 한국전력기술 주식회사 증기발생기 고수위 방지를 위한 안전주입 제어시스템
US11662126B2 (en) 2021-06-17 2023-05-30 Hewlett Packard Enterprise Development Lp Leak mitigation system
KR20240176195A (ko) 2023-06-15 2024-12-24 에이치엘만도 주식회사 전기 이동수단의 구동 모터 시스템 및 이를 포함하는 구동 시스템

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1459443A (en) * 1973-01-19 1976-12-22 Abtec Ltd Liquid level detecting devices
US4470948A (en) * 1981-11-04 1984-09-11 Westinghouse Electric Corp. Suppression of malfunction under water-solid conditions
US4692297A (en) * 1985-01-16 1987-09-08 Westinghouse Electric Corp. Control of nuclear reactor power plant on occurrence of rupture in coolant tubes
US4753771A (en) * 1986-02-07 1988-06-28 Westinghouse Electric Corp. Passive safety system for a pressurized water nuclear reactor
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
CZ283278B6 (cs) 1998-02-18
CN1080769A (zh) 1994-01-12
DE69313046T2 (de) 1998-02-26
EP0578392B1 (en) 1997-08-13
JP3194818B2 (ja) 2001-08-06
CZ124293A3 (en) 1994-03-16
US5309487A (en) 1994-05-03
DE69313046D1 (de) 1997-09-18
CN1041569C (zh) 1999-01-06
KR100300889B1 (ko) 2001-10-22
JPH0666985A (ja) 1994-03-11
KR940001175A (ko) 1994-01-10
EP0578392A1 (en) 1994-01-12

Similar Documents

Publication Publication Date Title
ES2108224T3 (es) Mitigacion de las rupturas de tubos de generadores de vapor en un reactor de agua presurizada con sistemas pasivos de seguridad.
US4560533A (en) Fast reactor power plant design having heat pipe heat exchanger
US4587080A (en) Compartmentalized safety coolant injection system
JPH0342595A (ja) 原子力発電プラント用の受動的安全注入装置
JPH0664171B2 (ja) 原子炉装置
EP0418701A1 (en) Reactor core decay heat removing system in a pressurized water reactor
JP2983290B2 (ja) 原子炉特に加圧水形原子炉の熱放出装置
SU537389A1 (ru) Система ограничени последствий аварии на атомных электростанци х
ES2368448T3 (es) Sistema de alimentación y procedimiento operativo correspondiente.
EP0388083B1 (en) Steam generator for sodium-cooled reactors
KR101374751B1 (ko) 유기유체를 이용한 잔열제거시스템과 잔열제거시스템의 구동방법
JPS6238393A (ja) 非常用炉心冷却方法及び装置
GB792972A (en) Control of atomic power reactors
US4190099A (en) Heat transfer system for the utilization of cavities dug in the subsoil as heat silos
GB1491232A (en) Nuclear reactors
JP2903819B2 (ja) 原子炉格納容器の圧力抑制設備
US4571323A (en) Cooling device
JP2548838B2 (ja) 加圧水型原子炉の炉心崩壊熱除去装置
US5178821A (en) Standby passive injection coolant water safety injection system for nuclear reactor plants
RU2108630C1 (ru) Энергетическая установка
RU2200990C2 (ru) Ядерная паропроизводительная установка с реактором, охлаждаемым водой под давлением
KR102352037B1 (ko) 과압방지부가 구비되는 원자로의 피동무한 냉각 구조체
KR20220018322A (ko) 원자로 장기 냉각 계통
RU2776024C1 (ru) Способ пассивного расхолаживания реакторной установки с реактором под давлением
KR960011210B1 (ko) 피동형 가압경수로

Legal Events

Date Code Title Description
FG2A Definitive protection

Ref document number: 578392

Country of ref document: ES