FR2283521A1 - Cooling system for suspending walls of reactor vessels - particularly liquid metal cooled fast neutron reactors - Google Patents

Cooling system for suspending walls of reactor vessels - particularly liquid metal cooled fast neutron reactors

Info

Publication number
FR2283521A1
FR2283521A1 FR7429647A FR7429647A FR2283521A1 FR 2283521 A1 FR2283521 A1 FR 2283521A1 FR 7429647 A FR7429647 A FR 7429647A FR 7429647 A FR7429647 A FR 7429647A FR 2283521 A1 FR2283521 A1 FR 2283521A1
Authority
FR
France
Prior art keywords
vessels
liquid metal
fast neutron
cooling
main vessel
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
FR7429647A
Other languages
French (fr)
Other versions
FR2283521B1 (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
Priority to FR7429647A priority Critical patent/FR2283521A1/en
Publication of FR2283521A1 publication Critical patent/FR2283521A1/en
Application granted granted Critical
Publication of FR2283521B1 publication Critical patent/FR2283521B1/fr
Granted legal-status Critical Current

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
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
    • G21C11/088—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation consisting of a stagnant or a circulating fluid
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Biomedical Technology (AREA)
  • General Health & Medical Sciences (AREA)
  • Molecular Biology (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

In a device for cooling the upwards extensions of the vessels of a fast neutron nuclear reactor, particularly a main vessel containing the reactor core and a volume of liquid metal coolant at high temperature and a safety vessel surrounding the main vessel, the two vessels being suspended from a rigid cover maintained at low temperature, a neutral gas circuit is provided in the annular space delimited by the two vessels and closed by an insulating structure extending parallel to the underside of the cover for cooling the wall of the main vessel, the wall of the safety vessel being cooled externally. A series of fans is mounted in the annular space for circulating the neutral gas. Prevents the thermosyphon effect arising from the heating of the neutral gas by the main vessel and the cooling by the cooled cover.
FR7429647A 1974-08-30 1974-08-30 Cooling system for suspending walls of reactor vessels - particularly liquid metal cooled fast neutron reactors Granted FR2283521A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7429647A FR2283521A1 (en) 1974-08-30 1974-08-30 Cooling system for suspending walls of reactor vessels - particularly liquid metal cooled fast neutron reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7429647A FR2283521A1 (en) 1974-08-30 1974-08-30 Cooling system for suspending walls of reactor vessels - particularly liquid metal cooled fast neutron reactors

Publications (2)

Publication Number Publication Date
FR2283521A1 true FR2283521A1 (en) 1976-03-26
FR2283521B1 FR2283521B1 (en) 1977-03-25

Family

ID=9142685

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7429647A Granted FR2283521A1 (en) 1974-08-30 1974-08-30 Cooling system for suspending walls of reactor vessels - particularly liquid metal cooled fast neutron reactors

Country Status (1)

Country Link
FR (1) FR2283521A1 (en)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2365863A1 (en) * 1976-09-27 1978-04-21 Westinghouse Electric Corp INSULATION AND PREHEATING PLANT FOR NUCLEAR REACTOR
EP0162338A1 (en) * 1984-05-03 1985-11-27 INTERATOM Gesellschaft mit beschränkter Haftung Vessel wall cooling for a liquid metal-cooled nuclear reactor
US4676947A (en) * 1983-10-28 1987-06-30 Novatome Device for thermal protection of a component of a fast-neutron nuclear reactor
WO2002007168A1 (en) * 2000-07-13 2002-01-24 Eskom Nuclear reactor
FR2832544A1 (en) * 2001-11-16 2003-05-23 Japan Nuclear Cycle Dev Inst THERMAL LOAD REDUCTION DEVICE IN A NUCLEAR REACTOR CONTAINER
FR2852139A1 (en) * 2003-03-04 2004-09-10 Japan Nuclear Cycle Dev Inst Nuclear reactor vessel heat load reduction system uses heat conducting element outside vessel covering zone above and below surface of liquid coolant
WO2013124398A1 (en) 2012-02-24 2013-08-29 Commissariat à l'énergie atomique et aux énergies alternatives System for discharging the residual power of a fast breeder nuclear reactor, using forced convection in the inter-vessel space

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
NEANT *

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2365863A1 (en) * 1976-09-27 1978-04-21 Westinghouse Electric Corp INSULATION AND PREHEATING PLANT FOR NUCLEAR REACTOR
US4676947A (en) * 1983-10-28 1987-06-30 Novatome Device for thermal protection of a component of a fast-neutron nuclear reactor
EP0162338A1 (en) * 1984-05-03 1985-11-27 INTERATOM Gesellschaft mit beschränkter Haftung Vessel wall cooling for a liquid metal-cooled nuclear reactor
WO2002007168A1 (en) * 2000-07-13 2002-01-24 Eskom Nuclear reactor
FR2832544A1 (en) * 2001-11-16 2003-05-23 Japan Nuclear Cycle Dev Inst THERMAL LOAD REDUCTION DEVICE IN A NUCLEAR REACTOR CONTAINER
FR2852139A1 (en) * 2003-03-04 2004-09-10 Japan Nuclear Cycle Dev Inst Nuclear reactor vessel heat load reduction system uses heat conducting element outside vessel covering zone above and below surface of liquid coolant
WO2013124398A1 (en) 2012-02-24 2013-08-29 Commissariat à l'énergie atomique et aux énergies alternatives System for discharging the residual power of a fast breeder nuclear reactor, using forced convection in the inter-vessel space
FR2987487A1 (en) * 2012-02-24 2013-08-30 Commissariat Energie Atomique SYSTEM FOR REMOVING THE RESIDUAL POWER OF A FAST NEUTRON NUCLEAR REACTOR USING FORCED CONVECTION IN THE INTERCUIVE SPACE

Also Published As

Publication number Publication date
FR2283521B1 (en) 1977-03-25

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Legal Events

Date Code Title Description
ST Notification of lapse