ES481818A1 - Perfeccionamientos en calderas nucleares de metal liquido caloportador. - Google Patents

Perfeccionamientos en calderas nucleares de metal liquido caloportador.

Info

Publication number
ES481818A1
ES481818A1 ES481818A ES481818A ES481818A1 ES 481818 A1 ES481818 A1 ES 481818A1 ES 481818 A ES481818 A ES 481818A ES 481818 A ES481818 A ES 481818A ES 481818 A1 ES481818 A1 ES 481818A1
Authority
ES
Spain
Prior art keywords
storage tank
reactor vessel
liquid
liquid metal
nuclear 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
Application number
ES481818A
Other languages
English (en)
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of ES481818A1 publication Critical patent/ES481818A1/es
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/904—Moderator, reflector, or coolant materials

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)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)

Abstract

Perfeccionamientos en calderas nucleares refrigeradas por un metal líquido, caracterizados porque comprenden un núcleo constituido por una pluralidad de montajes combustibles provistos de un pie tubular y por sus protecciones neutrónicas; una cuba principal que incluye, un fondo, una pared lateral y primeros medios de soportado dispuestos a un nivel dado, solidarizándose estos medios de la cara externa de la pared lateral; una cuba primaria interior y coaxial a la cuba principal que comprende un sistema de placas o rejillas de soporte apto para soportar y para alimentar el núcleo del reactor, una pared lateral y segundos medios de soportado solidarios respectivamente de la pared lateral de la cuba principal y de la cuba primaria y dispuestos en el nivel dado, definiendo las dos paredes laterales de las dos cubas entre sí un espacio anular; medios para crear una pared horizontal en el paso anular dispuestos sensiblemente en el nivel dado; al menos un intercambiador de calor exterior a las cubas apto para realizar un intercambio térmico entre el metal líquido y el agua ó vapor; un primer conducto de unión entre la entrada del ó de cada intercambiador y en el interior de la cuba primaria, desembocando el primer conducto en la cuba primaria por encima del núcleo y atravesando el espacio anular por encima de la pared horizontal por medios de travesía del espacio; un segundo conducto de unión entre la salida del ó de cada intercambiador y el espacio anular y que desemboca en el espacio anular por debajo de la pared horizontal para hacer circular el metal líquido frío en el mencionado sistema de soporte y después a través del núcleo partir de los pies de los ensamblajes combustibles; y medios para conectar una parte del metal líquido frío o introducirla en el espacio anular por encima de la pared.
ES481818A 1978-06-23 1979-06-22 Perfeccionamientos en calderas nucleares de metal liquido caloportador. Expired ES481818A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7818822A FR2429478A1 (fr) 1978-06-23 1978-06-23 Chaudiere nucleaire a neutrons rapides et a metal liquide caloporteur

Publications (1)

Publication Number Publication Date
ES481818A1 true ES481818A1 (es) 1980-08-16

Family

ID=9209907

Family Applications (1)

Application Number Title Priority Date Filing Date
ES481818A Expired ES481818A1 (es) 1978-06-23 1979-06-22 Perfeccionamientos en calderas nucleares de metal liquido caloportador.

Country Status (6)

Country Link
US (1) US4382907A (es)
EP (1) EP0006802B1 (es)
JP (1) JPS557692A (es)
DE (1) DE2963879D1 (es)
ES (1) ES481818A1 (es)
FR (1) FR2429478A1 (es)

Families Citing this family (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2429479A1 (fr) 1978-06-23 1980-01-18 Commissariat Energie Atomique Chaudiere nucleaire a neutrons rapides a metal liquide caloporteur
FR2506498B1 (fr) * 1981-05-22 1986-03-07 Commissariat Energie Atomique Reacteur nucleaire a neutrons rapides muni de dispositifs d'evacuation de la puissance residuelle
DE3266769D1 (en) * 1981-06-09 1985-11-14 Ivor Taylor Rowlands Nuclear power plant
USH119H (en) 1983-07-15 1986-09-02 The United States Of America As Represented By The United States Department Of Energy Passive emergency core cooling system for a liquid metal fast
US4576782A (en) * 1983-10-19 1986-03-18 Westinghouse Electric Corp. Nuclear reactor loss of coolant protection system
US5577085A (en) * 1995-04-24 1996-11-19 General Electric Company Boiling water reactor with compact containment and simplified safety systems
KR100597722B1 (ko) * 2004-01-02 2006-07-10 한국원자력연구소 액체금속로의 안정적인 피동 잔열제거 계통
KR100597723B1 (ko) * 2004-02-10 2006-07-10 한국원자력연구소 노심용융물 피동 냉각 및 가둠장치
JP2013526362A (ja) 2010-05-21 2013-06-24 ピエール サラドン 静脈切除術のための外科用鉗子
US9008257B2 (en) 2010-10-06 2015-04-14 Terrapower, Llc Electromagnetic flow regulator, system and methods for regulating flow of an electrically conductive fluid
US8781056B2 (en) * 2010-10-06 2014-07-15 TerraPower, LLC. Electromagnetic flow regulator, system, and methods for regulating flow of an electrically conductive fluid
US8584692B2 (en) 2010-10-06 2013-11-19 The Invention Science Fund I, Llc Electromagnetic flow regulator, system, and methods for regulating flow of an electrically conductive fluid
CN103174577A (zh) * 2013-03-13 2013-06-26 孔凡恒 一种分段利用江河水流发电的方法
CZ305830B6 (cs) * 2014-09-10 2016-03-30 ENERGOVĂťZKUM, spol. s.r.o. Zapojení parního generátoru v sodíkovém okruhu jaderného zařízení s rychlým reaktorem
RU2745348C1 (ru) * 2019-12-31 2021-03-24 Акционерное общество "АКМЭ-инжиниринг" (сокращенно АО "АКМЭ-инжиниринг") Ядерный реактор интегрального типа (варианты)
CN116072316A (zh) * 2023-01-09 2023-05-05 国科中子能(青岛)研究院有限公司 一种液态金属双循环模式反应堆装置

Family Cites Families (20)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL121726C (es) * 1960-01-20
BE638823A (es) * 1962-10-17
US3260649A (en) * 1964-05-28 1966-07-12 Wayne H Jens Nuclear reactor
FR6800M (es) 1964-07-16 1969-03-24
US3633784A (en) * 1968-02-09 1972-01-11 Westinghouse Electric Corp Hydrostatic reactor cavity seal
GB1258763A (es) * 1968-02-23 1971-12-30
US3768554A (en) * 1968-06-10 1973-10-30 Westinghouse Electric Corp Steam generator heated with liquid metal
DE2013586C3 (de) * 1970-03-21 1975-11-27 Gesellschaft Fuer Kernforschung Mbh, 7500 Karlsruhe Flüssigkeitsgekühlter Kernreaktor
US3718539A (en) * 1971-03-31 1973-02-27 Combustion Eng Passive nuclear reactor safeguard system
DE2217057C2 (de) 1972-04-08 1982-09-09 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Naturumlauf - Notkühlung für Kernreaktoren
US3924675A (en) * 1973-05-03 1975-12-09 Us Energy Energy absorber for sodium-heated heat exchanger
US3847773A (en) * 1973-06-11 1974-11-12 Technicon Instr Method and apparatus for curtain electrophoresis
DE2346868C2 (de) * 1973-09-18 1984-06-07 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Flüssigkeitsgekühlter Kernreaktor mit Schildwand zwischen Kühlmittelsammelraum und Druckbehälterwandung
FR2246942B1 (es) * 1973-10-03 1976-12-03 Commissariat Energie Atomique
US3912584A (en) * 1974-01-09 1975-10-14 Us Energy LMFBR with booster pump in pumping loop
US3941586A (en) * 1975-05-29 1976-03-02 The United States Of America As Represented By The United States Energy Research And Development Administration Method and apparatus for regenerating cold traps within liquid-metal systems
FR2333328A1 (fr) * 1975-11-26 1977-06-24 Commissariat Energie Atomique Reacteur nucleaire
US3994777A (en) * 1976-02-12 1976-11-30 The United States Of America As Represented By The United States Energy Research And Development Administration Nuclear reactor overflow line
JPS52104691A (en) * 1976-02-27 1977-09-02 Toshiba Corp Detecting apparatsu for nuclear fuel injury inside reactor
US4129476A (en) * 1976-07-28 1978-12-12 The United States Of America As Representedby The United States Department Of Energy Environment control system

Also Published As

Publication number Publication date
FR2429478A1 (fr) 1980-01-18
EP0006802A1 (fr) 1980-01-09
FR2429478B1 (es) 1982-03-26
DE2963879D1 (en) 1982-11-25
EP0006802B1 (fr) 1982-10-20
JPS557692A (en) 1980-01-19
US4382907A (en) 1983-05-10

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