FR3044156B1 - Dispositif de surete a declenchement passif pour reacteur nucleaire sur une baisse anormale du debit primaire - Google Patents

Dispositif de surete a declenchement passif pour reacteur nucleaire sur une baisse anormale du debit primaire

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Publication number
FR3044156B1
FR3044156B1 FR1561276A FR1561276A FR3044156B1 FR 3044156 B1 FR3044156 B1 FR 3044156B1 FR 1561276 A FR1561276 A FR 1561276A FR 1561276 A FR1561276 A FR 1561276A FR 3044156 B1 FR3044156 B1 FR 3044156B1
Authority
FR
France
Prior art keywords
lift
sheath
nuclear reactor
heat transfer
transfer fluid
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.)
Active
Application number
FR1561276A
Other languages
English (en)
Other versions
FR3044156A1 (fr
Inventor
Denis Lorenzo
Isabelle Guenot-Delahaie
Maxime Zabiego
Virasay Soukphouangkham
Bernard Valentin
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 FR1561276A priority Critical patent/FR3044156B1/fr
Priority to KR1020160156909A priority patent/KR20170059913A/ko
Priority to CN201611047719.6A priority patent/CN106941014B/zh
Priority to JP2016227540A priority patent/JP6948782B2/ja
Priority to RU2017101227A priority patent/RU2017101227A/ru
Publication of FR3044156A1 publication Critical patent/FR3044156A1/fr
Application granted granted Critical
Publication of FR3044156B1 publication Critical patent/FR3044156B1/fr
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/02Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/027Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/28Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • G21C17/022Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G21C17/025Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators for monitoring liquid metal coolants
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10Construction of control elements
    • G21C7/103Control assemblies containing one or more absorbants as well as other elements, e.g. fuel or moderator elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • G21D3/06Safety arrangements responsive to faults within the plant
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

La présente invention concerne un dispositif de sûreté à déclenchement passif pour réacteur nucléaire, le dispositif comprenant un assemblage comprenant : • un fourreau (200) destiné à être traversé longitudinalement par un fluide caloporteur ; • un équipage mobile (100), monté mobile en translation selon la direction longitudinale (3) dans le fourreau (200) et comprenant au moins une portion neutrophage ; l'équipage mobile (100) comprend une première portion de portance (110) et le fourreau (200) comprend une deuxième portion de portance (210), les première et deuxième portions de portance (110, 210) étant conformées de manière à ce que lorsque les première et deuxième portions de portance (110, 210) sont disposées en regard et que le débit Qf du fluide caloporteur traversant longitudinalement le fourreau (200) est supérieur à un débit Qdécienchement, alors le fluide caloporteur exerce sur l'équipage mobile (100) une force suffisante pour assurer la portance de l'équipage mobile dans le fourreau (200) et son maintien en configuration de portance et caractérisé en ce que la première (110) ou la deuxième (210) portion de portance forme un organe (112, 211) qui définit en partie au moins un amortisseur visqueux pour freiner la chute de l'équipage mobile 100 lors de sa chute.
FR1561276A 2015-11-23 2015-11-23 Dispositif de surete a declenchement passif pour reacteur nucleaire sur une baisse anormale du debit primaire Active FR3044156B1 (fr)

Priority Applications (5)

Application Number Priority Date Filing Date Title
FR1561276A FR3044156B1 (fr) 2015-11-23 2015-11-23 Dispositif de surete a declenchement passif pour reacteur nucleaire sur une baisse anormale du debit primaire
KR1020160156909A KR20170059913A (ko) 2015-11-23 2016-11-23 댐퍼를 가진 일차 유량의 비정상적 감소에 따른 원자로용 수동 발동 안전 장치
CN201611047719.6A CN106941014B (zh) 2015-11-23 2016-11-23 配备阻尼器的核反应堆的无源触发型安全装置
JP2016227540A JP6948782B2 (ja) 2015-11-23 2016-11-24 一次流量の異常低下に基づく原子炉用受動起動安全装置
RU2017101227A RU2017101227A (ru) 2015-11-23 2017-01-16 Защитное устройство пассивного срабатывания для ядерного реактора при ненормальном уменьшении первичного расхода

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR1561276A FR3044156B1 (fr) 2015-11-23 2015-11-23 Dispositif de surete a declenchement passif pour reacteur nucleaire sur une baisse anormale du debit primaire

Publications (2)

Publication Number Publication Date
FR3044156A1 FR3044156A1 (fr) 2017-05-26
FR3044156B1 true FR3044156B1 (fr) 2017-11-10

Family

ID=55486791

Family Applications (1)

Application Number Title Priority Date Filing Date
FR1561276A Active FR3044156B1 (fr) 2015-11-23 2015-11-23 Dispositif de surete a declenchement passif pour reacteur nucleaire sur une baisse anormale du debit primaire

Country Status (5)

Country Link
JP (1) JP6948782B2 (fr)
KR (1) KR20170059913A (fr)
CN (1) CN106941014B (fr)
FR (1) FR3044156B1 (fr)
RU (1) RU2017101227A (fr)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR3085531B1 (fr) 2018-09-05 2020-10-30 Commissariat Energie Atomique Structure etanche pour assemblage de maitrise de la reactivite de reacteur nucleaire a neutrons rapides
KR102600988B1 (ko) * 2022-03-28 2023-11-10 한국과학기술원 피동 안전 장치 및 핵연료 집합체

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2118852B1 (fr) * 1970-12-22 1973-11-30 Commissariat Energie Atomique
US3959072A (en) * 1973-09-27 1976-05-25 Combustion Engineering, Inc. Compactable control element assembly for a nuclear reactor
FR2353929A1 (fr) * 1976-05-31 1977-12-30 Alsacienne Atom Dispositif de securite intrinseque applicable au coeur d'un reacteur nucleaire a refrigerant liquide
US4313794A (en) * 1979-02-15 1982-02-02 Rockwell International Corporation Self-actuating and locking control for nuclear reactor
FR2503918B1 (fr) * 1981-04-09 1987-09-04 Commissariat Energie Atomique Barre absorbante pour reacteur nucleaire
JPS61118693A (ja) * 1984-11-15 1986-06-05 石川島播磨重工業株式会社 原子炉における制御棒の駆動装置
JP2003270375A (ja) * 2002-03-13 2003-09-25 Japan Atom Energy Res Inst 受動的原子炉停止機構
CN1182541C (zh) * 2002-11-14 2004-12-29 清华大学 带可调式磁阻尼器的反应堆控制棒驱动机构
FR2964237B1 (fr) * 2010-08-25 2012-09-28 Commissariat Energie Atomique Dispositif de mitigation des accidents graves pour assemblage de combustible nucleaire a efficacite amelioree
FR2983624B1 (fr) * 2011-12-02 2014-02-07 Commissariat Energie Atomique Assemblage pour reacteur nucleaire, comportant du combustible nucleaire et un systeme de declenchement et d'insertion d'au moins un element absorbant neutronique et/ou mitigateur
US9406406B2 (en) * 2011-12-12 2016-08-02 Bwxt Nuclear Energy, Inc. Control rod with outer hafnium skin
US20130272466A1 (en) * 2012-04-17 2013-10-17 Michael J. Edwards CRDM Divert Valve

Also Published As

Publication number Publication date
FR3044156A1 (fr) 2017-05-26
RU2017101227A (ru) 2018-07-17
KR20170059913A (ko) 2017-05-31
JP6948782B2 (ja) 2021-10-13
CN106941014B (zh) 2021-11-02
JP2017096954A (ja) 2017-06-01
CN106941014A (zh) 2017-07-11

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