ES438345A1 - Core support structure for a fast reactor - Google Patents
Core support structure for a fast reactorInfo
- Publication number
- ES438345A1 ES438345A1 ES438345A ES438345A ES438345A1 ES 438345 A1 ES438345 A1 ES 438345A1 ES 438345 A ES438345 A ES 438345A ES 438345 A ES438345 A ES 438345A ES 438345 A1 ES438345 A1 ES 438345A1
- Authority
- ES
- Spain
- Prior art keywords
- sleeper
- core
- ferrule
- tank
- assemblies
- 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.)
- Expired
Links
- 241001669679 Eleotris Species 0.000 abstract 6
- 230000000712 assembly Effects 0.000 abstract 3
- 238000000429 assembly Methods 0.000 abstract 3
- 229910001338 liquidmetal Inorganic materials 0.000 abstract 2
- 238000001816 cooling Methods 0.000 abstract 1
- 239000000446 fuel Substances 0.000 abstract 1
- 230000004927 fusion Effects 0.000 abstract 1
- 239000002184 metal Substances 0.000 abstract 1
- 238000000926 separation method Methods 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/10—Means for supporting the complete 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
- 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
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/016—Core catchers
-
- 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)
Abstract
Improvements introduced into a support structure for a fast-neutron nuclear reactor core, which includes a horizontal sleeper in which the feet of the fuel assemblies that form the core are inserted, this sleeper constituting a high-pressure collector for a liquid metal cooling system of these assemblies that circulates from the bottom to the top through the core, to collect in an internal tank, a perforated metal frame that supports the sleeper and is joined by its periphery to the internal surface of a main tank that surrounds the internal tank., and a core ashtray mounted under the sleeper and which includes a cylindrical side ferrule and a lower bottom that delimits an area containing a core collection plate in case of accidental fusion, characterized in that the ashtray ferrule includes at least a metallic separation wall arranged above the plate and dividing the space delimited by the ferrule into Two areas, one of which, between the wall and the sleeper, permanently collects liquid metal leaks from the sleeper at the foot of the assemblies, these leaks being channeled under the underside of the frame towards the surface of the main tank, and the other of which, between the wall and the bottom of the ash field, communicates with the outside of the ferrule by chimneys formed through the frame with the area delimited between the main tank and the internal tank. (Machine-translation by Google Translate, not legally binding)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7422095A FR2276663A1 (en) | 1974-06-25 | 1974-06-25 | SUPPORT STRUCTURE FOR QUICK NEUTRON NUCLEAR REACTOR CORE |
Publications (1)
Publication Number | Publication Date |
---|---|
ES438345A1 true ES438345A1 (en) | 1977-09-16 |
Family
ID=9140494
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES438345A Expired ES438345A1 (en) | 1974-06-25 | 1975-06-09 | Core support structure for a fast reactor |
Country Status (9)
Country | Link |
---|---|
JP (1) | JPS5117798A (en) |
BE (1) | BE828988A (en) |
DE (1) | DE2528120A1 (en) |
ES (1) | ES438345A1 (en) |
FR (1) | FR2276663A1 (en) |
GB (1) | GB1474646A (en) |
IT (1) | IT1032895B (en) |
NL (1) | NL7506153A (en) |
SE (1) | SE417766B (en) |
Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4116764A (en) * | 1976-02-11 | 1978-09-26 | The United States Of America As Represented By The United States Department Of Energy | Apparatus for controlling nuclear core debris |
FR2395567A1 (en) * | 1977-06-23 | 1979-01-19 | Commissariat Energie Atomique | HEART RECOVERY DEVICE FOR FAST NEUTRON NUCLEAR REACTOR |
JPS59126993A (en) * | 1983-01-12 | 1984-07-21 | 株式会社日立製作所 | Tank type fast breeder |
FR2558635B1 (en) * | 1984-01-24 | 1986-05-02 | Commissariat Energie Atomique | LIQUID METAL-COOLED NUCLEAR REACTOR CORE SUPPORT AND REFRIGERANT SUPPLY DEVICE |
DE3416398A1 (en) * | 1984-05-03 | 1985-11-07 | INTERATOM GmbH, 5060 Bergisch Gladbach | LIQUID METAL-COOLED CORE REACTOR WITH CORE SUPPORT STRUCTURE RELEASED BY HEAT TENSIONS |
WO2007099698A1 (en) | 2006-02-22 | 2007-09-07 | Kabushiki Kaisha Toshiba | Core catcher and its manufacturing method, and reactor container and its modifying method |
CN112635084A (en) * | 2020-12-09 | 2021-04-09 | 中国原子能科学研究院 | Sodium leakage receiving and inhibiting device for sodium-cooled fast reactor pit |
-
1974
- 1974-06-25 FR FR7422095A patent/FR2276663A1/en active Granted
-
1975
- 1975-05-13 BE BE156275A patent/BE828988A/en unknown
- 1975-05-15 IT IT68250/75A patent/IT1032895B/en active
- 1975-05-26 NL NL7506153A patent/NL7506153A/en not_active Application Discontinuation
- 1975-05-28 GB GB2331475A patent/GB1474646A/en not_active Expired
- 1975-06-09 ES ES438345A patent/ES438345A1/en not_active Expired
- 1975-06-18 SE SE7507061A patent/SE417766B/en unknown
- 1975-06-24 DE DE19752528120 patent/DE2528120A1/en active Pending
- 1975-06-25 JP JP50079299A patent/JPS5117798A/ja active Pending
Also Published As
Publication number | Publication date |
---|---|
FR2276663A1 (en) | 1976-01-23 |
JPS5117798A (en) | 1976-02-12 |
DE2528120A1 (en) | 1976-01-15 |
GB1474646A (en) | 1977-05-25 |
SE7507061L (en) | 1975-12-29 |
SE417766B (en) | 1981-04-06 |
BE828988A (en) | 1975-09-01 |
FR2276663B1 (en) | 1976-12-24 |
IT1032895B (en) | 1979-06-20 |
NL7506153A (en) | 1975-12-30 |
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