GB1462710A - Safety device for a nuclear reactor - Google Patents
Safety device for a nuclear reactorInfo
- Publication number
- GB1462710A GB1462710A GB4654674A GB4654674A GB1462710A GB 1462710 A GB1462710 A GB 1462710A GB 4654674 A GB4654674 A GB 4654674A GB 4654674 A GB4654674 A GB 4654674A GB 1462710 A GB1462710 A GB 1462710A
- Authority
- GB
- United Kingdom
- Prior art keywords
- damping system
- coolant
- absorber element
- reactor
- tube
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1462710 Controlling nuclear reactors COMMISSARIAT A L'ENERGIE ATOMIQUE 28 Oct 1974 [8 Nov 1973] 46546/74 Heading G6C A safety device in a nuclear reactor comprises an absorber element 18 having a head 20 releasably connected electromagnetically in a vertically movable operating stem 16; before release (Fig. 2), the element 18 is positioned in a tube 19 within the blanket zone 3 of the reactor and on release, falls into a position (Fig. 3) within the fuel zone 2, under the influence of a damping system and is supported by an abutment 27. The absorber element 18 may comprise links 24 of boron carbide enriched in B 10 . Holes 28 allow escape of liquid metal coolant when the element drops and may constitute the damping system. In a modification, Figs. 7a- 7b (not shown), a sleeve with a piston is provided at the top of head 20 as an alternative damping system. Operating means for stem 16 comprises a lead-screw and is described with reference to Figs. 4, 5 (not shown). The device is automatically releasable on deformation of the reactor core. Means comprising passages for the coolant and a spring may be provided, Fig. 6 (not shown), at the top of the tube 19 in order to permit automatic dropping of the absorber element in the event of abnormal reduction in the coolant flow rate.
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 |
|---|---|
| GB1462710A true GB1462710A (en) | 1977-01-26 |
Family
ID=9127460
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB4654674A Expired GB1462710A (en) | 1973-11-08 | 1974-10-28 | 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) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015500463A (en) * | 2011-12-02 | 2015-01-05 | コミッサリア ア レネルジー アトミーク エ オ ゼネルジ ザルタナテイヴ | Reactor assembly comprising nuclear fuel and a system for activating and inserting at least one neutron absorption and / or mitigation element |
| CN111916228A (en) * | 2020-07-31 | 2020-11-10 | 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) | Drive rod group on control rod drive mechanism and offshore reactor |
Families Citing this family (3)
| 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 |
-
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
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015500463A (en) * | 2011-12-02 | 2015-01-05 | コミッサリア ア レネルジー アトミーク エ オ ゼネルジ ザルタナテイヴ | Reactor assembly comprising nuclear fuel and a system for activating and inserting at least one neutron absorption and / or mitigation element |
| CN111916228A (en) * | 2020-07-31 | 2020-11-10 | 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) | Drive rod group on control rod drive mechanism and offshore reactor |
| 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 |
Also Published As
| Publication number | Publication date |
|---|---|
| ES431612A1 (en) | 1977-04-16 |
| BE821116A (en) | 1975-02-17 |
| FR2251079B1 (en) | 1976-12-03 |
| IT1024678B (en) | 1978-07-20 |
| FR2251079A1 (en) | 1975-06-06 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed | ||
| PCNP | Patent ceased through non-payment of renewal fee |