FR3044155B1 - 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 primaireInfo
- Publication number
- FR3044155B1 FR3044155B1 FR1561275A FR1561275A FR3044155B1 FR 3044155 B1 FR3044155 B1 FR 3044155B1 FR 1561275 A FR1561275 A FR 1561275A FR 1561275 A FR1561275 A FR 1561275A FR 3044155 B1 FR3044155 B1 FR 3044155B1
- Authority
- FR
- France
- Prior art keywords
- lift
- nuclear reactor
- sheath
- 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
Links
- 230000002159 abnormal effect Effects 0.000 title 1
- 239000013529 heat transfer fluid Substances 0.000 abstract 3
- 238000012423 maintenance Methods 0.000 abstract 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
-
- 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
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
- G21C17/025—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators for monitoring liquid metal coolants
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control 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
- G21C7/10—Construction of control elements
- G21C7/103—Control assemblies containing one or more absorbants as well as other elements, e.g. fuel or moderator elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/027—Means 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Particle Accelerators (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) longitudinalement décalée par rapport à la portion neutrophage 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.
Priority Applications (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR1561275A FR3044155B1 (fr) | 2015-11-23 | 2015-11-23 | Dispositif de surete a declenchement passif pour reacteur nucleaire sur une baisse anormale du debit primaire |
KR1020160156908A KR20170059912A (ko) | 2015-11-23 | 2016-11-23 | 일차 유량의 비정상적 감소에 따른 원자로용 수동 발동 안전 장치 |
CN201611047649.4A CN107068213B (zh) | 2015-11-23 | 2016-11-23 | 用于冷却剂量异常减少时的核反应堆无源触发型安全装置 |
JP2016227528A JP6948781B2 (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 |
RU2017101216A RU2017101216A (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 |
---|---|---|---|
FR1561275A FR3044155B1 (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 |
---|---|
FR3044155A1 FR3044155A1 (fr) | 2017-05-26 |
FR3044155B1 true FR3044155B1 (fr) | 2017-11-10 |
Family
ID=55486790
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR1561275A Active FR3044155B1 (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) | JP6948781B2 (fr) |
KR (1) | KR20170059912A (fr) |
CN (1) | CN107068213B (fr) |
FR (1) | FR3044155B1 (fr) |
RU (1) | RU2017101216A (fr) |
Families Citing this family (2)
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 |
CN110752044B (zh) * | 2019-11-21 | 2021-11-02 | 中国核动力研究设计院 | 一种内部通水的控制棒 |
Family Cites Families (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE633586A (fr) * | 1962-06-13 | 1900-01-01 | ||
FR2118852B1 (fr) * | 1970-12-22 | 1973-11-30 | Commissariat Energie Atomique | |
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 |
RU2069019C1 (ru) * | 1993-04-21 | 1996-11-10 | Физико-энергетический институт | Сборка пассивной аварийной защиты с гидравлически взвешенным стержнем для реактора с жидким теплоносителем |
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 |
US9911513B2 (en) * | 2014-01-14 | 2018-03-06 | Ge-Hitachi Nuclear Energy Americas Llc | Passive shutdown system and method of operating a liquid metal cooled reactor using the same |
-
2015
- 2015-11-23 FR FR1561275A patent/FR3044155B1/fr active Active
-
2016
- 2016-11-23 CN CN201611047649.4A patent/CN107068213B/zh active Active
- 2016-11-23 KR KR1020160156908A patent/KR20170059912A/ko unknown
- 2016-11-24 JP JP2016227528A patent/JP6948781B2/ja active Active
-
2017
- 2017-01-16 RU RU2017101216A patent/RU2017101216A/ru not_active Application Discontinuation
Also Published As
Publication number | Publication date |
---|---|
KR20170059912A (ko) | 2017-05-31 |
JP2017096953A (ja) | 2017-06-01 |
RU2017101216A (ru) | 2018-07-16 |
FR3044155A1 (fr) | 2017-05-26 |
JP6948781B2 (ja) | 2021-10-13 |
CN107068213B (zh) | 2021-11-02 |
CN107068213A (zh) | 2017-08-18 |
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