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
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.
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)
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 |
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 |
US9984777B2 (en) * | 2007-11-15 | 2018-05-29 | Nuscale Power, Llc | Passive emergency feedwater system |
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***强化换热方法及装置 |
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 |
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***自动快速冷却方法 |
US9303865B2 (en) | 2013-09-18 | 2016-04-05 | Skavis Corporation | Steam generation apparatus and associated control system and methods for startup |
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 |
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*** |
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*** |
JP7075885B2 (ja) | 2015-08-25 | 2022-05-26 | バイクテック アーゲー | 遠隔制御ユニットおよび電気自転車 |
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 |
CN109994230A (zh) * | 2019-04-12 | 2019-07-09 | 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***及方法 |
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*** |
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*** |
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 |
Family Cites Families (5)
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 |
-
1992
- 1992-06-24 US US07/903,683 patent/US5309487A/en not_active Expired - Lifetime
-
1993
- 1993-06-16 ES ES93304675T patent/ES2108224T3/es not_active Expired - Lifetime
- 1993-06-16 EP EP93304675A patent/EP0578392B1/en not_active Expired - Lifetime
- 1993-06-16 DE DE69313046T patent/DE69313046T2/de not_active Expired - Lifetime
- 1993-06-22 CZ CZ931242A patent/CZ283278B6/cs not_active IP Right Cessation
- 1993-06-23 KR KR1019930011539A patent/KR100300889B1/ko not_active IP Right Cessation
- 1993-06-23 CN CN93107437A patent/CN1041569C/zh not_active Expired - Lifetime
- 1993-06-24 JP JP18081293A patent/JP3194818B2/ja not_active Expired - Lifetime
Also Published As
Publication number | Publication date |
---|---|
JPH0666985A (ja) | 1994-03-11 |
US5309487A (en) | 1994-05-03 |
KR940001175A (ko) | 1994-01-10 |
KR100300889B1 (ko) | 2001-10-22 |
DE69313046D1 (de) | 1997-09-18 |
JP3194818B2 (ja) | 2001-08-06 |
CZ283278B6 (cs) | 1998-02-18 |
DE69313046T2 (de) | 1998-02-26 |
CN1041569C (zh) | 1999-01-06 |
EP0578392B1 (en) | 1997-08-13 |
EP0578392A1 (en) | 1994-01-12 |
CN1080769A (zh) | 1994-01-12 |
CZ124293A3 (en) | 1994-03-16 |
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 | |
ES2368448T3 (es) | Sistema de alimentación y procedimiento operativo correspondiente. | |
RU2078384C1 (ru) | Безопасная ядерная установка | |
EP0418701B1 (en) | Reactor core decay heat removing system in a pressurized water reactor | |
JPH0664171B2 (ja) | 原子炉装置 | |
KR910003287B1 (ko) | 구획화된 냉각재 안전 주입 시스템 | |
US3649451A (en) | Nuclear reactor containment system | |
CN110097981A (zh) | 用于非能动冷却核电站冷却剂存储器的设备 | |
JP2983290B2 (ja) | 原子炉特に加圧水形原子炉の熱放出装置 | |
US4983353A (en) | Novel passive approach to protecting the primary containment barrier formed by the intermediate heat exchanger from the effects of an uncontrolled sodium water reaction | |
KR101374751B1 (ko) | 유기유체를 이용한 잔열제거시스템과 잔열제거시스템의 구동방법 | |
US3446188A (en) | Steam generator or heater for an atomic power generating plant | |
JPS6238393A (ja) | 非常用炉心冷却方法及び装置 | |
SU581892A3 (ru) | Ядерна энергетическа установка | |
GB792972A (en) | Control of atomic power reactors | |
CN116052908A (zh) | 一种核反应堆 | |
GB1491232A (en) | Nuclear reactors | |
JP2903819B2 (ja) | 原子炉格納容器の圧力抑制設備 | |
KR102381886B1 (ko) | 원자로 장기 냉각 계통 | |
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 | |
KR102352037B1 (ko) | 과압방지부가 구비되는 원자로의 피동무한 냉각 구조체 | |
CN214253887U (zh) | 一种非能动余热排出***及具有余热排出的核电厂 | |
US4519978A (en) | Secondary heat transfer circuit for a nuclear reactor |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
FG2A | Definitive protection |
Ref document number: 578392 Country of ref document: ES |