FR3044156B1 - PASSIVE TRIP SECURITY DEVICE FOR NUCLEAR REACTOR ON ABNORMAL PRIMARY RATE DROP - Google Patents
PASSIVE TRIP SECURITY DEVICE FOR NUCLEAR REACTOR ON ABNORMAL PRIMARY RATE DROPInfo
- 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
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
-
- 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
- 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
- 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
- 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
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.The present invention relates to a passive tripping safety device for a nuclear reactor, the device comprising an assembly comprising: • a sheath (200) intended to be traversed longitudinally by a heat transfer fluid; • a mobile unit (100), mounted mobile in translation in the longitudinal direction (3) in the sheath (200) and comprising at least one neutron absorbing portion; the mobile unit (100) comprises a first lift portion (110) and the sheath (200) comprises a second lift portion (210), the first and second lift portions (110, 210) being shaped so as to that when the first and second lift portions (110, 210) are arranged facing each other and the flow rate Qf of the heat transfer fluid passing longitudinally through the sheath (200) is greater than a flow rate Qécienquement, then the heat transfer fluid exerts on the mobile unit (100) sufficient force to ensure the lift of the movable assembly in the sheath (200) and its maintenance in the lift configuration and characterized in that the first (110) or the second (210) lift portion forms a member (112, 211) which partly defines at least one viscous damper to slow down the fall of the mobile equipment 100 during its fall.
Priority Applications (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR1561276A FR3044156B1 (en) | 2015-11-23 | 2015-11-23 | PASSIVE TRIP SECURITY DEVICE FOR NUCLEAR REACTOR ON ABNORMAL PRIMARY RATE DROP |
CN201611047719.6A CN106941014B (en) | 2015-11-23 | 2016-11-23 | Passive triggering safety device for nuclear reactor equipped with damper |
KR1020160156909A KR20170059913A (en) | 2015-11-23 | 2016-11-23 | Passive activation safety device for nuclear reactor on abnormal dropping in primary flow with a damper |
JP2016227540A JP6948782B2 (en) | 2015-11-23 | 2016-11-24 | Passive start safety device for nuclear reactors based on abnormal decrease in primary flow rate |
RU2017101227A RU2017101227A (en) | 2015-11-23 | 2017-01-16 | PROTECTIVE DEVICE FOR PASSIVE OPERATION FOR A NUCLEAR REACTOR WITH AN ABNORMAL REDUCTION OF THE PRIMARY COSTS |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR1561276A FR3044156B1 (en) | 2015-11-23 | 2015-11-23 | PASSIVE TRIP SECURITY DEVICE FOR NUCLEAR REACTOR ON ABNORMAL PRIMARY RATE DROP |
Publications (2)
Publication Number | Publication Date |
---|---|
FR3044156A1 FR3044156A1 (en) | 2017-05-26 |
FR3044156B1 true FR3044156B1 (en) | 2017-11-10 |
Family
ID=55486791
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR1561276A Active FR3044156B1 (en) | 2015-11-23 | 2015-11-23 | PASSIVE TRIP SECURITY DEVICE FOR NUCLEAR REACTOR ON ABNORMAL PRIMARY RATE DROP |
Country Status (5)
Country | Link |
---|---|
JP (1) | JP6948782B2 (en) |
KR (1) | KR20170059913A (en) |
CN (1) | CN106941014B (en) |
FR (1) | FR3044156B1 (en) |
RU (1) | RU2017101227A (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR3085531B1 (en) | 2018-09-05 | 2020-10-30 | Commissariat Energie Atomique | WATERPROOF STRUCTURE FOR ASSEMBLY FOR CONTROL OF THE REACTIVITY OF A QUICK NEUTRON NUCLEAR REACTOR |
KR102600988B1 (en) * | 2022-03-28 | 2023-11-10 | 한국과학기술원 | Passive safety apparatus and nuclear fuel assembly |
Family Cites Families (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2118852B1 (en) * | 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 (en) * | 1976-05-31 | 1977-12-30 | Alsacienne Atom | INTRINSIC SAFETY DEVICE APPLICABLE TO THE CORE OF A LIQUID REFRIGERANT NUCLEAR REACTOR |
US4313794A (en) * | 1979-02-15 | 1982-02-02 | Rockwell International Corporation | Self-actuating and locking control for nuclear reactor |
FR2503918B1 (en) * | 1981-04-09 | 1987-09-04 | Commissariat Energie Atomique | ABSORBENT BAR FOR NUCLEAR REACTOR |
JPS61118693A (en) * | 1984-11-15 | 1986-06-05 | 石川島播磨重工業株式会社 | Method of driving control rod in nuclear reactor |
JP2003270375A (en) * | 2002-03-13 | 2003-09-25 | Japan Atom Energy Res Inst | Passive reactor shutdown mechanism |
CN1182541C (en) * | 2002-11-14 | 2004-12-29 | 清华大学 | Reactor control-rod driving mechanism with adjustable magnetic damper |
FR2964237B1 (en) * | 2010-08-25 | 2012-09-28 | Commissariat Energie Atomique | DEVICE FOR MITIGATION OF SERIOUS ACCIDENTS FOR ASSEMBLY OF NUCLEAR FUEL WITH IMPROVED EFFICIENCY |
FR2983624B1 (en) * | 2011-12-02 | 2014-02-07 | Commissariat Energie Atomique | NUCLEAR REACTOR ASSEMBLY HAVING NUCLEAR FUEL AND A SYSTEM FOR TRIGGERING AND INSERTING AT LEAST ONE NEUTRONIC ABSORBING ELEMENT AND / OR MITIGATOR |
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 |
-
2015
- 2015-11-23 FR FR1561276A patent/FR3044156B1/en active Active
-
2016
- 2016-11-23 KR KR1020160156909A patent/KR20170059913A/en unknown
- 2016-11-23 CN CN201611047719.6A patent/CN106941014B/en active Active
- 2016-11-24 JP JP2016227540A patent/JP6948782B2/en active Active
-
2017
- 2017-01-16 RU RU2017101227A patent/RU2017101227A/en not_active Application Discontinuation
Also Published As
Publication number | Publication date |
---|---|
CN106941014A (en) | 2017-07-11 |
RU2017101227A (en) | 2018-07-17 |
CN106941014B (en) | 2021-11-02 |
KR20170059913A (en) | 2017-05-31 |
JP6948782B2 (en) | 2021-10-13 |
JP2017096954A (en) | 2017-06-01 |
FR3044156A1 (en) | 2017-05-26 |
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