ES2041004T3 - Enfriamiento del nucleo por emergencia pasiva a plena presion y sistema de retirada del calor residual para reactores nucleares refrigerados por agua. - Google Patents

Enfriamiento del nucleo por emergencia pasiva a plena presion y sistema de retirada del calor residual para reactores nucleares refrigerados por agua.

Info

Publication number
ES2041004T3
ES2041004T3 ES198989306757T ES89306757T ES2041004T3 ES 2041004 T3 ES2041004 T3 ES 2041004T3 ES 198989306757 T ES198989306757 T ES 198989306757T ES 89306757 T ES89306757 T ES 89306757T ES 2041004 T3 ES2041004 T3 ES 2041004T3
Authority
ES
Spain
Prior art keywords
water
tank
duct
residual heat
primary
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
ES198989306757T
Other languages
English (en)
Inventor
Frederick James Gardner
Rodney Strong
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.)
Rolls Royce Submarines Ltd
Original Assignee
Rolls Royce Marine Power Operations Ltd
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 Rolls Royce Marine Power Operations Ltd filed Critical Rolls Royce Marine Power Operations Ltd
Application granted granted Critical
Publication of ES2041004T3 publication Critical patent/ES2041004T3/es
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/322—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed above the core
    • 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
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

UN REACTOR NUCLEAR ENFRIADO POR AGUA (10) CONSTA DE UN NUCLEO (14), UN CIRCUITO PRIMARIO DE ENFRIAMIENTO DEL AGUA (24,26) Y UN PRESIONIZADOR (46), QUE FORMAN UNA UNIDAD EN UNA SOLA PIEZA EN UN RECIPIENTE A PRESION (12). SE PROPORCIONA UN SISTEMA DE ENFRIAMIENTO PASIVO DEL NUCLEO DE EMERGENCIA A PRESION TOTAL Y DE EXTRACCION DEL CALOR RESIDUAL, QUE CONSTA DE UN TANQUE (58) PROVISTO DE UN ALIMENTACION DE AGUA DE RESERVA SITUADO POR ENCIMA DEL CICUITO PRIMARIO DE ENFRIAMIENTO DEL AGUA (24,26) O DEL NUCLEO DEL REACTOR. EL TANQUE (58) ESTA INTERCONECTADO CON EL CIRCUITO PRIMARIO DE AGUA DE ENFRIAMIENTO MEDIANTE UN PRIMER CONDUCTO (74) Y UN SEGUNDO CONDUCTO (68). EL PRIMER CONDUCTO (74) TIENE UN ADOBLEZ EN FORMA DE U INVERTIDA QUE PASA A TRAVES DE UN ESPACIO DE AGUA (48) Y UN ESPACIO DE VAPOR (50) DEL PRESIONIZADOR (46) PARA FORMAR UN CIERRE DE VAPOR (78). EL PRIMER CONDUCTO (74) Y EL SEGUNDO CONDUCTO (68) ESTAN DOTADOS ASIMISMO DE UNOS CIERRES HERMETICOS TERMO-HIDROSTATICOS (82 Y 70). EL TANQUE (58) TIENE UNO O MAS CIRCUITOS DE EXTRACCION DEL CALOR RESIDUAL QUE COMPRENDEN UN INTERCAMBIADOR DE CALOR (60) POSICIONADO EN EL TANQUE (58) Y UN INTERCAMBIADOR DE CALOR (62) POR EL EXTERIOR DEL TANQUE (58). EL DESPLAZAMIENTO DEL CIERRE DE VAPOR (78) DE LA DOBLEZ EN FORMA DE U INVERTIDA (76) POSIBILITA QUE EL AGUA FRIA DEL TANQUE (58) FLUYA DENTRO DEL CIRCUITO PRIMARIO DE ENFRIAMIENTO DEL AGUA Y QUE AQUELLA SE ENFRIE. EL CIERRE DE VAPOR (78) DETECTA LAS ANORMALIDADES EXISTENTES EN EL NUCLEO DEL REACTOR (14) Y EN EL CIRCUITO PRIMARIO DE ENFRIAMIENTO DEL AGUA (24,26), ASI COMO EN EL NIVEL DE AGUA DEL PRESIONIZADOR, INICIANDO AUTOMATICAMENTE EL ENFRIAMIENTO PASIVO DE EMERGENCIA A PRESION TOTAL Y LA EXTRACCION DEL CALOR RESIDUAL.
ES198989306757T 1988-07-21 1989-07-04 Enfriamiento del nucleo por emergencia pasiva a plena presion y sistema de retirada del calor residual para reactores nucleares refrigerados por agua. Expired - Lifetime ES2041004T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB888817394A GB8817394D0 (en) 1988-07-21 1988-07-21 Full pressure passive emergency core cooling and residual heat removal system for water cooled nuclear reactors

Publications (1)

Publication Number Publication Date
ES2041004T3 true ES2041004T3 (es) 1993-11-01

Family

ID=10640875

Family Applications (1)

Application Number Title Priority Date Filing Date
ES198989306757T Expired - Lifetime ES2041004T3 (es) 1988-07-21 1989-07-04 Enfriamiento del nucleo por emergencia pasiva a plena presion y sistema de retirada del calor residual para reactores nucleares refrigerados por agua.

Country Status (7)

Country Link
US (1) US5102616A (es)
EP (1) EP0353867B1 (es)
JP (1) JPH03502005A (es)
DE (1) DE68906727T2 (es)
ES (1) ES2041004T3 (es)
GB (1) GB8817394D0 (es)
WO (1) WO1990001207A1 (es)

Families Citing this family (44)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB8923864D0 (en) * 1989-10-24 1989-12-13 Rolls Royce & Ass An improved water cooled nuclear reactor and pressuriser assembly
US5255296A (en) * 1992-06-24 1993-10-19 Westinghouse Electric Corp. Collecting and recirculating condensate in a nuclear reactor containment
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
JP2002156485A (ja) * 2000-11-15 2002-05-31 Hitachi Ltd 原子炉
US6795518B1 (en) * 2001-03-09 2004-09-21 Westinghouse Electric Company Llc Integral PWR with diverse emergency cooling and method of operating same
DE10156495C1 (de) * 2001-11-16 2003-01-02 Framatome Anp Gmbh Vorrichtung und Verfahren zum Kühlen eines Reaktordruckbehälters einer Siedewasser-Reaktoranlage
FR2832846B1 (fr) * 2001-11-26 2005-12-09 Commissariat Energie Atomique Reacteur nucleaire compact a eau sous pression
ATE400878T1 (de) * 2003-04-16 2008-07-15 Areva Np Gmbh Kerntechnische anlage und verfahren zum betrieb einer kerntechnischen anlage
DE102005057249A1 (de) * 2005-11-29 2007-05-31 Framatome Anp Gmbh Einspeisesystem und zugehöriges Betriebsverfahren
US8170173B2 (en) 2007-11-15 2012-05-01 The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University Passive emergency feedwater system
US9984777B2 (en) 2007-11-15 2018-05-29 Nuscale Power, Llc Passive emergency feedwater system
US9330796B2 (en) 2007-11-15 2016-05-03 Nuscale Power, Llc Stable startup system for a nuclear reactor
US8891723B2 (en) * 2007-11-15 2014-11-18 State of Oregon Acting by and Through The State Board of Higher Education on Behalf or Oregon State University, The Oregon State University Stable startup system for a nuclear reactor
JP4592773B2 (ja) * 2008-02-29 2010-12-08 株式会社東芝 静的冷却減圧系および加圧水型原子力プラント
US8437446B2 (en) * 2008-11-17 2013-05-07 Nuscale Power, Llc Steam generator flow by-pass system
EP2534660A1 (en) 2010-02-05 2012-12-19 Smr, Llc Nuclear reactor system having natural circulation of primary coolant
US8781057B2 (en) * 2010-12-16 2014-07-15 Babcock & Wilcox Mpower, Inc. Control system and method for pressurized water reactor (PWR) and PWR systems including same
US8638898B2 (en) * 2011-03-23 2014-01-28 Babcock & Wilcox Mpower, Inc. Emergency core cooling system for pressurized water reactor
US20120314829A1 (en) * 2011-06-08 2012-12-13 UB-Battelle, LLC Thermal energy integration and storage system
US9583221B2 (en) 2011-06-15 2017-02-28 Bwxt Nuclear Energy, Inc. Integrated emergency core cooling system condenser for pressurized water reactor
US8867690B2 (en) * 2011-08-25 2014-10-21 Babcock & Wilcox Mpower, Inc. Pressurized water reactor with compact passive safety systems
KR101229953B1 (ko) * 2011-09-08 2013-02-06 한전원자력연료 주식회사 사용후핵연료 저장조 피동형 냉각장치
FR2985841B1 (fr) * 2012-01-18 2014-02-21 Technicatome Systeme d'evacuation de la puissance residuelle d'un reacteur nucleaire a eau sous pression
US9620252B2 (en) 2012-04-17 2017-04-11 Bwxt Mpower, Inc. Island mode for nuclear power plant
US9728281B2 (en) 2012-04-17 2017-08-08 Bwxt Mpower, Inc. Auxiliary condenser system for decay heat removal in a nuclear reactor
US10529457B2 (en) 2012-04-17 2020-01-07 Bwxt Mpower, Inc. Defense in depth safety paradigm for nuclear reactor
US11901088B2 (en) 2012-05-04 2024-02-13 Smr Inventec, Llc Method of heating primary coolant outside of primary coolant loop during a reactor startup operation
US9786394B2 (en) * 2012-05-21 2017-10-10 Smr Inventec, Llc Component cooling water system for nuclear power plant
US9275761B2 (en) * 2012-06-13 2016-03-01 Westinghouse Electric Company Llc Small modular reactor safety systems
US9748004B2 (en) * 2012-06-13 2017-08-29 Westinghouse Electric Company Llc Combined core makeup tank and heat removal system for a small modular pressurized water reactor
FR3001572B1 (fr) * 2013-01-25 2015-02-27 Technicatome Reacteur nucleaire a eau pressurisee de type integre comportant un pressuriseur integre.
US11373768B2 (en) 2013-03-12 2022-06-28 Bwxt Mpower, Inc. Refueling water storage tank (RWST) with tailored passive emergency core cooling (ECC) flow
CN105431908B (zh) 2013-03-15 2017-09-22 BWXT m动力股份有限公司 用于长期反应堆冷却的无源技术
US9779840B2 (en) 2013-10-28 2017-10-03 Bwxt Mpower, Inc. PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
US9997262B2 (en) * 2013-12-26 2018-06-12 Nuscale Power, Llc Integral reactor pressure vessel tube sheet
US9805833B2 (en) 2014-01-06 2017-10-31 Bwxt Mpower, Inc. Passively initiated depressurization valve for light water reactor
CN104269193B (zh) * 2014-09-18 2017-02-08 中广核研究院有限公司 次临界能源包层事故缓解系统
US10685752B2 (en) 2015-02-10 2020-06-16 Nuscale Power, Llc Steam generator with inclined tube sheet
FR3062235B1 (fr) * 2017-01-26 2019-06-07 Societe Technique Pour L'energie Atomique Reacteur nucleaire integrant un echangeur de chaleur primaire de securite
US10859550B2 (en) * 2017-05-16 2020-12-08 Bryan Szatkowski Thermal surface casing vent-steam condensing gas and fluid flow rate-collection manifold
CN109712726B (zh) * 2017-10-25 2024-03-26 中国船舶重工集团公司第七一九研究所 一种海洋核动力平台反应堆余热排出系统
GB2568692B (en) * 2017-11-23 2020-01-22 Rolls Royce Plc Nuclear power plants
CN109659046A (zh) * 2019-02-01 2019-04-19 中国原子能科学研究院 耦合的反应堆余热导出系统
CN114414277B (zh) * 2022-01-13 2023-11-24 上海发电设备成套设计研究院有限责任公司 一种浸没试验系统装置及试验方法

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL121726C (es) * 1960-01-20
US3566904A (en) * 1969-04-15 1971-03-02 Atomic Energy Commission Liquid flow control system
DE2304700A1 (de) * 1973-01-31 1974-08-01 Siemens Ag Druckwasserreaktor
SE435432B (sv) * 1981-03-30 1984-09-24 Asea Atom Ab Kernreaktoranleggning med gaskudde som avgrensning mellan kylvatten och omgivande bassengvatten
SE8401711L (sv) * 1984-03-28 1985-09-29 Asea Atom Ab Tryckvattenreaktor innehallande en trycksatt basseng
DE3571358D1 (en) * 1984-05-07 1989-08-10 Westinghouse Electric Corp Small unitized pressurized water nuclear reactor
CH664037A5 (de) * 1984-07-17 1988-01-29 Sulzer Ag Anlage mit einem nuklearen heizreaktor.
WO1986001632A1 (en) * 1984-09-05 1986-03-13 Vecsey Georg Method for the passive retransmission of heat in nuclear reactors
US4728486A (en) * 1985-08-14 1988-03-01 Westinghouse Electric Corp. Pressurized water nuclear reactor pressure control system and method of operating same
US4753771A (en) * 1986-02-07 1988-06-28 Westinghouse Electric Corp. Passive safety system for a pressurized water nuclear reactor

Also Published As

Publication number Publication date
EP0353867A1 (en) 1990-02-07
US5102616A (en) 1992-04-07
DE68906727T2 (de) 1993-09-09
EP0353867B1 (en) 1993-05-26
GB8817394D0 (en) 1989-07-05
JPH03502005A (ja) 1991-05-09
WO1990001207A1 (en) 1990-02-08
DE68906727D1 (de) 1993-07-01

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