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ES8103871A1 - Perfeccionamientos en circuitos caloportadores secundarios para reactores nucleares - Google Patents

Perfeccionamientos en circuitos caloportadores secundarios para reactores nucleares

Info

Publication number
ES8103871A1
ES8103871A1 ES488410A ES488410A ES8103871A1 ES 8103871 A1 ES8103871 A1 ES 8103871A1 ES 488410 A ES488410 A ES 488410A ES 488410 A ES488410 A ES 488410A ES 8103871 A1 ES8103871 A1 ES 8103871A1
Authority
ES
Spain
Prior art keywords
liquid
metal
tank
steam
generator
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
ES488410A
Other languages
English (en)
Other versions
ES488410A0 (es
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.)
Electricite de France SA
Original Assignee
Electricite de France SA
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
Priority claimed from FR7903335A external-priority patent/FR2448767A1/fr
Application filed by Electricite de France SA filed Critical Electricite de France SA
Publication of ES488410A0 publication Critical patent/ES488410A0/es
Publication of ES8103871A1 publication Critical patent/ES8103871A1/es
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/04—Pumping arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • 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)
  • Structures Of Non-Positive Displacement Pumps (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

CIRCUITO CALOPORTADOR SECUNDARIO DE UN REACTOR NUCLEAR REFRIGERADO POR UN METAL LIQUIDO. COMPRENDE AL MENOS UN INTERCAMBIADOR INTERMEDIO (4) ALOJADO EN EL REACTOR, UN GENERADOR DE VAPOR EXTERIOR (6), UNA BOMBA DE CIRCULACION DEL SODIO SECUNDARIO (12) DEL TIPO DE NIVEL LIBRE, ELECTROMAGNETICA, CON LA ENTRADA SUMERGIDA EN EL DEPOSITO DEL METAL LIQUIDO (24''), COLOCADO ESTE EN EL NIVEL MAS BAJO DE LA INSTALACION. LA ENTRADA DE LA BOMBA SE COLOCA A LA SALIDA DEL GENERADOR DE VAPOR (6) Y LA SALIDA SE ACOPLA AL INTERCAMBIADOR INTERMEDIO (4). LA PARTE SUPERIOR DE LA ENVOLVENTE DEL GENERADOR DE VAPOR CONSTITUYE UN DEPOSITO ANTIARIETE, ANTERIOR AL GENERADOR DE VAPOR. EL CONDUCTO DE IMPULSION (10) ESTA ACOTADO Y PRESENTA UN PUNTO INFERIOR EN EL DEPOSITO (24'''') SITUADO POR DEBAJO DEL NIVEL DEL LIQUIDO.
ES488410A 1979-02-09 1980-02-08 Perfeccionamientos en circuitos caloportadores secundarios para reactores nucleares Expired ES8103871A1 (es)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR7903335A FR2448767A1 (fr) 1979-02-09 1979-02-09 Circuit caloporteur secondaire pour reacteur nucleaire refroidi par du sodium liquide
FR7906595A FR2451616A2 (fr) 1979-02-09 1979-03-15 Perfectionnements aux circuits caloporteurs secondaires pour reacteurs nucleaires refroidis par du sodium liquide

Publications (2)

Publication Number Publication Date
ES488410A0 ES488410A0 (es) 1981-02-16
ES8103871A1 true ES8103871A1 (es) 1981-02-16

Family

ID=26221008

Family Applications (1)

Application Number Title Priority Date Filing Date
ES488410A Expired ES8103871A1 (es) 1979-02-09 1980-02-08 Perfeccionamientos en circuitos caloportadores secundarios para reactores nucleares

Country Status (7)

Country Link
US (1) US4293385A (es)
EP (1) EP0014662B1 (es)
JP (1) JPS55138698A (es)
CA (1) CA1143485A (es)
DE (1) DE3060509D1 (es)
ES (1) ES8103871A1 (es)
FR (1) FR2451616A2 (es)

Families Citing this family (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2486296B1 (fr) * 1980-07-04 1986-06-06 Electricite De France Reacteur nucleaire refroidi par un metal liquide
US4367194A (en) * 1980-09-22 1983-01-04 The United States Of America As Represented By The United States Department Of Energy Emergency core cooling system
FR2533355B1 (fr) * 1982-09-22 1988-07-08 Commissariat Energie Atomique Circuit caloporteur secondaire pour un reacteur nucleaire refroidi par un metal liquide et generateur de vapeur adapte a un tel circuit
FR2533354A1 (fr) * 1982-09-22 1984-03-23 Commissariat Energie Atomique Circuit caloporteur secondaire pour un reacteur nucleaire a metal liquide
FR2544053B1 (fr) * 1983-04-07 1985-06-28 Commissariat Energie Atomique Generateur de vapeur pour reacteur refroidi par un metal liquide
JPH06103353B2 (ja) * 1984-06-14 1994-12-14 株式会社東芝 液体金属冷却型原子炉の冷却装置
US8132410B2 (en) * 2007-12-17 2012-03-13 Battelle Energy Alliance, Llc Methods and systems for the production of hydrogen
KR100944080B1 (ko) 2008-04-29 2010-02-24 한국원자력연구원 액체 금속 및 물을 이용하는 장치로부터의 이송 시스템 및그 작동 방법
KR100944081B1 (ko) 2008-04-30 2010-02-24 한국원자력연구원 가열 시스템 및 가열 방법
US9786395B2 (en) 2011-04-25 2017-10-10 Holtec International, Inc. Air-cooled heat exchanger and system and method of using the same to remove waste thermal energy from radioactive materials
US11504814B2 (en) 2011-04-25 2022-11-22 Holtec International Air cooled condenser and related methods
WO2014089072A2 (en) 2012-12-03 2014-06-12 Holtec International, Inc. Brazing compositions and uses thereof
CN104464844B (zh) * 2014-12-08 2017-03-15 中广核工程有限公司 核电站冷链系统设冷水出水温度调节方法
RU2691755C2 (ru) * 2017-07-24 2019-06-18 Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" Способ организации естественной циркуляции жидкометаллического теплоносителя ядерного реактора на быстрых нейтронах
CN113096838B (zh) * 2021-05-18 2025-05-06 西安热工研究院有限公司 一种管道内液态金属排出及管道快速降温装置
US11662126B2 (en) 2021-06-17 2023-05-30 Hewlett Packard Enterprise Development Lp Leak mitigation system

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1471970A (fr) * 1965-03-31 1967-03-03 English Electric Co Ltd Ensemble de pompage pour pomper du métal liquide
FR1556449A (es) * 1967-01-27 1969-02-07
GB1224320A (en) * 1967-12-05 1971-03-10 English Electric Co Ltd Liquid-metal cooled nuclear reactors
CH535476A (de) * 1969-11-26 1973-03-31 Prvni Brnenska Strojirna Anlage zum Umwälzen von flüssigem Metall
US3956063A (en) * 1971-05-28 1976-05-11 The United States Of America As Represented By The United States Energy Research And Development Administration Emergency core cooling system for a fast reactor
FR2246028B1 (es) * 1973-10-02 1979-05-04 Electricite De France
US3951738A (en) * 1974-05-10 1976-04-20 Westinghouse Electric Corporation Nuclear reactor coolant and cover gas system
FR2321750A1 (fr) * 1975-08-22 1977-03-18 Commissariat Energie Atomique Perfectionnement apporte aux circuits secondaires d'un reacteur nucleaire
CH608126A5 (es) * 1976-03-29 1978-12-15 Commissariat Energie Atomique
FR2379881A1 (fr) * 1977-02-04 1978-09-01 Commissariat Energie Atomique Bloc-pompe echangeur de chaleur pour reacteurs nucleaires

Also Published As

Publication number Publication date
JPH024877B2 (es) 1990-01-30
ES488410A0 (es) 1981-02-16
DE3060509D1 (en) 1982-07-29
JPS55138698A (en) 1980-10-29
CA1143485A (en) 1983-03-22
EP0014662B1 (fr) 1982-06-09
EP0014662A1 (fr) 1980-08-20
US4293385A (en) 1981-10-06
FR2451616B2 (es) 1982-01-15
FR2451616A2 (fr) 1980-10-10

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19970401