FR2454676A1 - Dispositif de recuperation de fuites dans une enceinte contenant des installations nucleaires contenant ou circulant du sodium liquide - Google Patents

Dispositif de recuperation de fuites dans une enceinte contenant des installations nucleaires contenant ou circulant du sodium liquide

Info

Publication number
FR2454676A1
FR2454676A1 FR7909764A FR7909764A FR2454676A1 FR 2454676 A1 FR2454676 A1 FR 2454676A1 FR 7909764 A FR7909764 A FR 7909764A FR 7909764 A FR7909764 A FR 7909764A FR 2454676 A1 FR2454676 A1 FR 2454676A1
Authority
FR
France
Prior art keywords
sodium
leakages
liq
cases
recovering
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.)
Granted
Application number
FR7909764A
Other languages
English (en)
Other versions
FR2454676B1 (fr
Inventor
Pierre Expert
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
Application filed by Electricite de France SA filed Critical Electricite de France SA
Priority to FR7909764A priority Critical patent/FR2454676B1/fr
Publication of FR2454676A1 publication Critical patent/FR2454676A1/fr
Application granted granted Critical
Publication of FR2454676B1 publication Critical patent/FR2454676B1/fr
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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • 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)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

DISPOSITIF DE RECUPERATION DES FUITES DE SODIUM LIQUIDE SUSCEPTIBLES DE SURVENIR DANS UN MATERIEL CONTENANT OU CIRCULANT DU SODIUM LIQUIDE, LEDIT MATERIEL ETANT LOGE DANS UNE ENCEINTE DE CONFINEMENT. IL COMPREND UNE STRUCTURE FORMANT PLANCHER POUR L'ENCEINTE ET PRESENTANT UN POINT BAS UNIQUE; UN PREMIER RESERVOIR DE VOLUME REDUIT LOGE EN DESSOUS DU PLANCHER QUI EST MUNI D'UNE PREMIERE CONDUITE RACCORDANT LA PARTIE SUPERIEURE DUDIT RESERVOIR AU POINT BAS; UN DEUXIEME RESERVOIR DE VOLUME PLUS IMPORTANT LOGE EN DESSOUS DUDIT PLANCHER ET APTE A RECUEILLIR LA QUASI TOTALITE DU SODIUM CONTENU DANS LEDIT MATERIEL MUNI D'UNE DEUXIEME CONDUITE RACCORDANT SA PARTIE SUPERIEURE A L'INTERIEUR DE LADITE ENCEINTE, L'EXTREMITE SUPERIEURE DE LADITE DEUXIEME CONDUITE DEBOUCHANT AU-DESSUS DUDIT POINT BAS. APPLICATION A UNE INSTALLATION NUCLEAIRE REFROIDIE PAR DU SODIUM LIQUIDE.
FR7909764A 1979-04-18 1979-04-18 Dispositif de recuperation de fuites dans une enceinte contenant des installations nucleaires contenant ou circulant du sodium liquide Expired FR2454676B1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7909764A FR2454676B1 (fr) 1979-04-18 1979-04-18 Dispositif de recuperation de fuites dans une enceinte contenant des installations nucleaires contenant ou circulant du sodium liquide

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7909764A FR2454676B1 (fr) 1979-04-18 1979-04-18 Dispositif de recuperation de fuites dans une enceinte contenant des installations nucleaires contenant ou circulant du sodium liquide

Publications (2)

Publication Number Publication Date
FR2454676A1 true FR2454676A1 (fr) 1980-11-14
FR2454676B1 FR2454676B1 (fr) 1986-01-31

Family

ID=9224436

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7909764A Expired FR2454676B1 (fr) 1979-04-18 1979-04-18 Dispositif de recuperation de fuites dans une enceinte contenant des installations nucleaires contenant ou circulant du sodium liquide

Country Status (1)

Country Link
FR (1) FR2454676B1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4356869A (en) * 1980-12-19 1982-11-02 The United States Of America As Represented By The United States Department Of Energy Fire suppressing apparatus

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1501544A1 (de) * 1966-07-21 1969-10-23 Interatom Waermetauscheranlage fuer die Austauschmedien Fluessigmetall/Wasser
US3718539A (en) * 1971-03-31 1973-02-27 Combustion Eng Passive nuclear reactor safeguard system

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1501544A1 (de) * 1966-07-21 1969-10-23 Interatom Waermetauscheranlage fuer die Austauschmedien Fluessigmetall/Wasser
US3718539A (en) * 1971-03-31 1973-02-27 Combustion Eng Passive nuclear reactor safeguard system

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
EXBK/76 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4356869A (en) * 1980-12-19 1982-11-02 The United States Of America As Represented By The United States Department Of Energy Fire suppressing apparatus

Also Published As

Publication number Publication date
FR2454676B1 (fr) 1986-01-31

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Legal Events

Date Code Title Description
ST Notification of lapse