FR3104311B1 - Réacteur nucléaire refroidi au métal liquide intégrant un système complètement passif d’évacuation de la puissance résiduelle (EPUR) - Google Patents

Réacteur nucléaire refroidi au métal liquide intégrant un système complètement passif d’évacuation de la puissance résiduelle (EPUR) Download PDF

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Publication number
FR3104311B1
FR3104311B1 FR1913942A FR1913942A FR3104311B1 FR 3104311 B1 FR3104311 B1 FR 3104311B1 FR 1913942 A FR1913942 A FR 1913942A FR 1913942 A FR1913942 A FR 1913942A FR 3104311 B1 FR3104311 B1 FR 3104311B1
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FR
France
Prior art keywords
liquid metal
heat removal
nuclear reactor
epur
completely passive
Prior art date
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Active
Application number
FR1913942A
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English (en)
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FR3104311A1 (fr
Inventor
Paul Gauthe
Alessandro Pantano
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 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.)
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Publication date
Application filed by Commissariat a lEnergie Atomique et aux Energies Alternatives CEA filed Critical Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Priority to FR1913942A priority Critical patent/FR3104311B1/fr
Priority to JP2020203309A priority patent/JP7050886B2/ja
Priority to US17/116,363 priority patent/US11636956B2/en
Publication of FR3104311A1 publication Critical patent/FR3104311A1/fr
Application granted granted Critical
Publication of FR3104311B1 publication Critical patent/FR3104311B1/fr
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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
    • G21C15/24—Promoting flow of the coolant
    • G21C15/26—Promoting flow of the coolant by convection, e.g. using chimneys, using divergent channels
    • 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
    • G21C15/24—Promoting flow of the coolant
    • G21C15/243—Promoting flow of the coolant for liquids
    • G21C15/247—Promoting flow of the coolant for liquids for liquid metals
    • 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
    • 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
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • G21C15/185—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps using energy stored in reactor system
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D20/00—Heat storage plants or apparatus in general; Regenerative heat-exchange apparatus not covered by groups F28D17/00 or F28D19/00
    • F28D20/02—Heat storage plants or apparatus in general; Regenerative heat-exchange apparatus not covered by groups F28D17/00 or F28D19/00 using latent heat
    • F28D20/023—Heat storage plants or apparatus in general; Regenerative heat-exchange apparatus not covered by groups F28D17/00 or F28D19/00 using latent heat the latent heat storage material being enclosed in granular particles or dispersed in a porous, fibrous or cellular structure
    • 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
    • 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)
  • Manufacture And Refinement Of Metals (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

Réacteur nucléaire refroidi au métal liquide intégrant un système complètement passif d’évacuation de la puissance résiduelle (EPUR). L’invention concerne un réacteur nucléaire (1) à neutrons rapides refroidi avec du métal liquide, comprenant un système (2) d’évacuation d’au moins une partie à la fois de la puissance nominale et de la puissance résiduelle du réacteur qui garantit à la fois: - une évacuation de la puissance résiduelle de manière totalement passive dès l’instant initial de l’accident ; - une évacuation de la chaleur à travers la cuve primaire ; - la mise en œuvre d’une source froide finale (réservoir avec matériau MCP) autre que les échangeurs du type sodium/air ou NaK/air, utilisés selon l’état de l’art. Figure pour l’abrégé : Fig.2
FR1913942A 2019-12-09 2019-12-09 Réacteur nucléaire refroidi au métal liquide intégrant un système complètement passif d’évacuation de la puissance résiduelle (EPUR) Active FR3104311B1 (fr)

Priority Applications (3)

Application Number Priority Date Filing Date Title
FR1913942A FR3104311B1 (fr) 2019-12-09 2019-12-09 Réacteur nucléaire refroidi au métal liquide intégrant un système complètement passif d’évacuation de la puissance résiduelle (EPUR)
JP2020203309A JP7050886B2 (ja) 2019-12-09 2020-12-08 完全に受動的な残留力除去（ｄｈｒ）システムを組み込んだ液体金属冷却原子炉
US17/116,363 US11636956B2 (en) 2019-12-09 2020-12-09 Liquid metal-cooled nuclear reactor incorporating a completely passive residual power removal (DHR) system

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR1913942A FR3104311B1 (fr) 2019-12-09 2019-12-09 Réacteur nucléaire refroidi au métal liquide intégrant un système complètement passif d’évacuation de la puissance résiduelle (EPUR)
FR1913942 2019-12-09

Publications (2)

Publication Number Publication Date
FR3104311A1 FR3104311A1 (fr) 2021-06-11
FR3104311B1 true FR3104311B1 (fr) 2021-12-03

Family

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FR1913942A Active FR3104311B1 (fr) 2019-12-09 2019-12-09 Réacteur nucléaire refroidi au métal liquide intégrant un système complètement passif d’évacuation de la puissance résiduelle (EPUR)

Country Status (3)

Country Link
US (1) US11636956B2 (fr)
JP (1) JP7050886B2 (fr)
FR (1) FR3104311B1 (fr)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11508488B2 (en) * 2020-09-10 2022-11-22 Battelle Energy Alliance, Llc Heat transfer systems for nuclear reactor cores, and related systems
FR3127840B1 (fr) 2021-10-05 2024-01-12 Commissariat Energie Atomique Réacteur nucléaire refroidi au métal liquide intégrant un système complètement passif d’évacuation de la puissance résiduelle (EPUR) à source froide modulaire.
FR3131060B1 (fr) 2021-12-16 2023-12-08 Commissariat Energie Atomique Réacteur nucléaire refroidi au métal liquide intégrant un système passif d’évacuation de la puissance résiduelle (EPUR) à source froide avec réservoir thermique à matériau à changement de phase (MCP) et couche isolante thermique amovible autour du réservoir à MCP.
WO2024091724A2 (fr) * 2022-08-19 2024-05-02 Abilene Christian University Système de gestion thermique de réacteur nucléaire

Family Cites Families (16)

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GB1258763A (fr) * 1968-02-23 1971-12-30
GB1256874A (fr) * 1968-02-23 1971-12-15
US4361009A (en) * 1979-10-31 1982-11-30 The Babcock & Wilcox Company Moving bed heat storage and recovery system
FR2541496A1 (fr) * 1983-02-22 1984-08-24 Commissariat Energie Atomique Reacteur nucleaire a neutrons rapides a structure interne allegee
NO159879C (no) * 1986-05-02 1989-02-15 Santo As Fremgangsm te ved drift av et forbrenningsanlegg, segg for utfoerelse ten.
JPH02210295A (ja) * 1989-02-10 1990-08-21 Toshiba Corp 補助炉心冷却装置
KR100597722B1 (ko) * 2004-01-02 2006-07-10 한국원자력연구소 액체금속로의 안정적인 피동 잔열제거 계통
ITTO20070052A1 (it) * 2007-01-24 2008-07-25 Luciano Cinotti Sistema di evacuazione del calore residuo da un reattore nucleare
ATE498811T1 (de) * 2008-07-01 2011-03-15 Sener Ing & Sist Dualwärmeenergiespeichertank
FR2965655B1 (fr) * 2010-10-04 2012-10-19 Commissariat Energie Atomique Perfectionnement a un reacteur nucleaire sfr de type integre
JP2012093282A (ja) 2010-10-28 2012-05-17 Toshiba Corp 炉心溶融物の保持装置
JP2013076675A (ja) 2011-09-30 2013-04-25 Toshiba Corp 液体金属冷却原子炉用受動冷却システム
JP2013104711A (ja) 2011-11-11 2013-05-30 Toshiba Corp 液体金属冷却原子炉
KR20150108999A (ko) 2014-03-18 2015-10-01 한국과학기술원 루프형 써모사이펀을 이용한 액체금속로 외벽냉각 장치
WO2018007739A1 (fr) * 2016-07-05 2018-01-11 Commissariat A L'energie Atomique Et Aux Energies Alternatives Réacteur nucléaire intégré à neutrons rapides comportant un dispositif de verrouillage passif du chemin hydraulique
KR101984767B1 (ko) * 2017-11-13 2019-05-31 (주)에너지허브 캡슐형태의 상변환물질을 이용한 피동냉각 열교환 시스템

Also Published As

Publication number Publication date
JP7050886B2 (ja) 2022-04-08
FR3104311A1 (fr) 2021-06-11
JP2021092566A (ja) 2021-06-17
US20210210229A1 (en) 2021-07-08
US11636956B2 (en) 2023-04-25

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