FR2987487B1 - SYSTEM FOR REMOVING THE RESIDUAL POWER OF A FAST NEUTRON NUCLEAR REACTOR USING FORCED CONVECTION IN THE INTERCUIVE SPACE - Google Patents

SYSTEM FOR REMOVING THE RESIDUAL POWER OF A FAST NEUTRON NUCLEAR REACTOR USING FORCED CONVECTION IN THE INTERCUIVE SPACE

Info

Publication number
FR2987487B1
FR2987487B1 FR1251706A FR1251706A FR2987487B1 FR 2987487 B1 FR2987487 B1 FR 2987487B1 FR 1251706 A FR1251706 A FR 1251706A FR 1251706 A FR1251706 A FR 1251706A FR 2987487 B1 FR2987487 B1 FR 2987487B1
Authority
FR
France
Prior art keywords
intercuive
space
nuclear reactor
forced convection
fast neutron
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 - Fee Related
Application number
FR1251706A
Other languages
French (fr)
Other versions
FR2987487A1 (en
Inventor
Guy Marie Gautier
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
Commissariat a lEnergie Atomique et aux Energies Alternatives 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, Commissariat a lEnergie Atomique et aux Energies Alternatives CEA filed Critical Commissariat a lEnergie Atomique CEA
Priority to FR1251706A priority Critical patent/FR2987487B1/en
Priority to PCT/EP2013/053520 priority patent/WO2013124398A1/en
Publication of FR2987487A1 publication Critical patent/FR2987487A1/en
Application granted granted Critical
Publication of FR2987487B1 publication Critical patent/FR2987487B1/en
Expired - Fee Related legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • 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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • 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
    • 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
    • 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

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)
FR1251706A 2012-02-24 2012-02-24 SYSTEM FOR REMOVING THE RESIDUAL POWER OF A FAST NEUTRON NUCLEAR REACTOR USING FORCED CONVECTION IN THE INTERCUIVE SPACE Expired - Fee Related FR2987487B1 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
FR1251706A FR2987487B1 (en) 2012-02-24 2012-02-24 SYSTEM FOR REMOVING THE RESIDUAL POWER OF A FAST NEUTRON NUCLEAR REACTOR USING FORCED CONVECTION IN THE INTERCUIVE SPACE
PCT/EP2013/053520 WO2013124398A1 (en) 2012-02-24 2013-02-22 System for discharging the residual power of a fast breeder nuclear reactor, using forced convection in the inter-vessel space

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR1251706A FR2987487B1 (en) 2012-02-24 2012-02-24 SYSTEM FOR REMOVING THE RESIDUAL POWER OF A FAST NEUTRON NUCLEAR REACTOR USING FORCED CONVECTION IN THE INTERCUIVE SPACE

Publications (2)

Publication Number Publication Date
FR2987487A1 FR2987487A1 (en) 2013-08-30
FR2987487B1 true FR2987487B1 (en) 2014-03-28

Family

ID=47754486

Family Applications (1)

Application Number Title Priority Date Filing Date
FR1251706A Expired - Fee Related FR2987487B1 (en) 2012-02-24 2012-02-24 SYSTEM FOR REMOVING THE RESIDUAL POWER OF A FAST NEUTRON NUCLEAR REACTOR USING FORCED CONVECTION IN THE INTERCUIVE SPACE

Country Status (2)

Country Link
FR (1) FR2987487B1 (en)
WO (1) WO2013124398A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR3143827A1 (en) 2022-12-15 2024-06-21 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear reactor cooled with liquid metal or molten salt(s) integrating a residual power evacuation system (EPuR) through the primary reactor vessel, comprising a module of pivoting fins with passive or active triggering, located in the inter-tank space.

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2283521A1 (en) * 1974-08-30 1976-03-26 Commissariat Energie Atomique Cooling system for suspending walls of reactor vessels - particularly liquid metal cooled fast neutron reactors
GB2157880B (en) * 1984-04-19 1988-02-10 Westinghouse Electric Corp An improved nuclear reactor plant construction
US5499277A (en) 1994-08-19 1996-03-12 General Electric Company Method and apparatus for enhancing reactor air-cooling system performance

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR3143827A1 (en) 2022-12-15 2024-06-21 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear reactor cooled with liquid metal or molten salt(s) integrating a residual power evacuation system (EPuR) through the primary reactor vessel, comprising a module of pivoting fins with passive or active triggering, located in the inter-tank space.

Also Published As

Publication number Publication date
FR2987487A1 (en) 2013-08-30
WO2013124398A1 (en) 2013-08-29

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Legal Events

Date Code Title Description
ST Notification of lapse

Effective date: 20151030