ES431612A1 - Safety device for a nuclear reactor - Google Patents
Safety device for a nuclear reactorInfo
- Publication number
- ES431612A1 ES431612A1 ES431612A ES431612A ES431612A1 ES 431612 A1 ES431612 A1 ES 431612A1 ES 431612 A ES431612 A ES 431612A ES 431612 A ES431612 A ES 431612A ES 431612 A1 ES431612 A1 ES 431612A1
- Authority
- ES
- Spain
- Prior art keywords
- absorbent element
- box
- core
- area
- safety device
- 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
Classifications
-
- 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
- G21C7/12—Means for moving control elements to desired position
-
- 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
-
- 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)
Abstract
Safety device for a fast neutron nuclear reactor, comprising an absorbent element provided with a support head, connected by a disconnectable link to the lower end of an axially mobile vertical maneuvering rod, this absorbent element being capable, after breaking the disconnectable link, falling by gravity from a high position to a low position, in a delimited passage through the reactor core by a box open at its upper end, and arranged in the core between other boxes containing a nuclear fuel, and delimiting in the core cooled by upward circulation of a liquid metal, a central fuel area and a peripheral cover area, which completely surrounds the central area, characterized in that the disconnectable link between the head of the absorbent element and the end of the maneuvering rod is arranged, in the high position of the element, in the upper part, and at least partially in n the interior of the open box, the absorbent element extending in this box in the peripheral cover area outside the central area. (Machine-translation by Google Translate, not legally binding)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7339717A FR2251079B1 (en) | 1973-11-08 | 1973-11-08 |
Publications (1)
Publication Number | Publication Date |
---|---|
ES431612A1 true ES431612A1 (en) | 1977-04-16 |
Family
ID=9127460
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES431612A Expired ES431612A1 (en) | 1973-11-08 | 1974-11-04 | Safety device for a nuclear reactor |
Country Status (5)
Country | Link |
---|---|
BE (1) | BE821116A (en) |
ES (1) | ES431612A1 (en) |
FR (1) | FR2251079B1 (en) |
GB (1) | GB1462710A (en) |
IT (1) | IT1024678B (en) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2387495A1 (en) * | 1977-04-15 | 1978-11-10 | Commissariat Energie Atomique | NUCLEAR REACTOR SAFETY DEVICE |
FR2507809A1 (en) * | 1981-06-10 | 1982-12-17 | Commissariat Energie Atomique | Safety device for control rod in nuclear reactor - where rod is pushed downwards in its sleeve if accident or earthquake occurs |
FR2586500B1 (en) * | 1985-08-22 | 1987-10-30 | Commissariat Energie Atomique | ABSORBENT ELEMENT FOR FAST NEUTRAL NUCLEAR REACTOR |
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 |
CN111916228B (en) * | 2020-07-31 | 2023-06-06 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Driving rod group on control rod driving mechanism and offshore reactor |
-
1973
- 1973-11-08 FR FR7339717A patent/FR2251079B1/fr not_active Expired
-
1974
- 1974-10-16 BE BE149569A patent/BE821116A/en not_active IP Right Cessation
- 1974-10-24 IT IT70162/74A patent/IT1024678B/en active
- 1974-10-28 GB GB4654674A patent/GB1462710A/en not_active Expired
- 1974-11-04 ES ES431612A patent/ES431612A1/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
IT1024678B (en) | 1978-07-20 |
FR2251079B1 (en) | 1976-12-03 |
GB1462710A (en) | 1977-01-26 |
BE821116A (en) | 1975-02-17 |
FR2251079A1 (en) | 1975-06-06 |
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