GB1412514A - Safety device for a nuclear reactor - Google Patents
Safety device for a nuclear reactorInfo
- Publication number
- GB1412514A GB1412514A GB2613073A GB2613073A GB1412514A GB 1412514 A GB1412514 A GB 1412514A GB 2613073 A GB2613073 A GB 2613073A GB 2613073 A GB2613073 A GB 2613073A GB 1412514 A GB1412514 A GB 1412514A
- Authority
- GB
- United Kingdom
- Prior art keywords
- container
- core
- gas
- reactor
- compartment
- 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
- 239000006096 absorbing agent Substances 0.000 abstract 3
- 229910052580 B4C Inorganic materials 0.000 abstract 2
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 abstract 2
- 239000000843 powder Substances 0.000 abstract 2
- 230000000717 retained effect Effects 0.000 abstract 2
- 229910052770 Uranium Inorganic materials 0.000 abstract 1
- 230000000694 effects Effects 0.000 abstract 1
- 230000004907 flux Effects 0.000 abstract 1
- 239000000155 melt Substances 0.000 abstract 1
- 230000004048 modification Effects 0.000 abstract 1
- 238000012986 modification Methods 0.000 abstract 1
- 230000003252 repetitive effect Effects 0.000 abstract 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 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
-
- 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)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1412514 Nuclear reactor safety apparatus GROUPEMENT POUR LES ACTIVITIES ATOMIQUES ET AVANCEES 31 May 1973 [2 June 1972] 26130/73 Heading G6C Nuclear reactor safety apparatus comprises a container intended to be disposed in the reactor with its lower part in the core and neutron absorber retained in an upper part above the core, the lower part having an aperture extending to the outside of the container and normally sealed by a closure member, certain reactor conditions causing unsealing of the aperture to result in the neutron absorber moving into the lower part. In one embodiment (Fig. 1) the container 1 is internally partitioned into three compartments 4, 5, 6 and contains a central tube 7 leading to a gas-inlet valve 8 and a sealed opening 9. A conduit 10 penetrates the bottom wall of the container 1 and is sealed by a brazed in uranium plug 11. Gas is supplied to the interior of the container 1 via valve 8 and, by repetitive pressurisation and depressurization boron carbide powder 20 in the lower compartment 4 is raised into the intermediate compartment 5 to lie on the turns of a helical blade 17. Gas is stored in the upper compartment 6 under pressure. In operation, with an increase in neutron flux in the core causing a rise in temperature thereof, the braze melts, plug 11 is expelled causing depressurization of the lower compartment 4 and the powder 20 moves rapidly from the intermediate compartment 5 (above the core) to the lower compartment 4 (in the core). In another embodiment (Fig. 2) a block 23 of sintered boron carbide is retained by frangible elements 25 in the upper part 22 of the container 1 whose lower part mounts a shock-absorber 26. The interior of the container 1 is pressurized by gas injected through valve 29. In the event of expulsion of the closure plug 28, gas pressure above the block 23 causes the elements 25 to break and the block 23 to fall to the lower part 21 (in the core). In a modification (not shown) for use in a gascooled reactor, the bottom aperture is sealed by a frangible diaphragm and the container contains gas at reactor pressure. In the event of loss of reactor pressure, the diaphragm ruptures.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7219990A FR2188248B1 (en) | 1972-06-02 | 1972-06-02 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1412514A true GB1412514A (en) | 1975-11-05 |
Family
ID=9099636
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB2613073A Expired GB1412514A (en) | 1972-06-02 | 1973-05-31 | Safety device for a nuclear reactor |
Country Status (10)
| Country | Link |
|---|---|
| JP (1) | JPS5627840B2 (en) |
| BE (1) | BE799908A (en) |
| BR (1) | BR7304122D0 (en) |
| CA (1) | CA1003976A (en) |
| DE (1) | DE2327778A1 (en) |
| FR (1) | FR2188248B1 (en) |
| GB (1) | GB1412514A (en) |
| IT (1) | IT990583B (en) |
| NL (1) | NL7307712A (en) |
| SE (1) | SE411267B (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4104121A (en) * | 1972-06-02 | 1978-08-01 | Groupement Atomique Alsacienne Atlantique | Solid absorbent safety device for a nuclear reactor |
| JPS52145427A (en) * | 1976-05-28 | 1977-12-03 | Central Glass Co Ltd | Method of moulding solidified concrete product and mould used therefor |
| JPS56115987A (en) * | 1980-02-19 | 1981-09-11 | Tokyo Shibaura Electric Co | Nuclear reactor shuttdown device |
| FR3087292B1 (en) * | 2018-10-12 | 2020-10-02 | Commissariat Energie Atomique | NUCLEAR REACTOR ASSEMBLY CONTAINING A WATERPROOF ENCLOSURE |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2855899A (en) * | 1956-05-02 | 1958-10-14 | Ben J Beaty | Device for controlling insertion of rod |
| NL277872A (en) * | 1961-05-05 | |||
| NL295855A (en) * | 1962-07-27 | 1900-01-01 | ||
| JPS4322789Y1 (en) * | 1967-06-26 | 1968-09-25 |
-
1972
- 1972-06-02 FR FR7219990A patent/FR2188248B1/fr not_active Expired
-
1973
- 1973-05-23 BE BE1005079A patent/BE799908A/en unknown
- 1973-05-25 IT IT24568/73A patent/IT990583B/en active
- 1973-05-30 DE DE2327778*A patent/DE2327778A1/en not_active Ceased
- 1973-05-31 GB GB2613073A patent/GB1412514A/en not_active Expired
- 1973-06-01 JP JP6105773A patent/JPS5627840B2/ja not_active Expired
- 1973-06-01 SE SE7307811A patent/SE411267B/en unknown
- 1973-06-01 NL NL7307712A patent/NL7307712A/xx not_active Application Discontinuation
- 1973-06-01 BR BR4122/73A patent/BR7304122D0/en unknown
- 1973-06-01 CA CA172,979A patent/CA1003976A/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| FR2188248A1 (en) | 1974-01-18 |
| FR2188248B1 (en) | 1974-12-27 |
| CA1003976A (en) | 1977-01-18 |
| DE2327778A1 (en) | 1973-12-20 |
| BR7304122D0 (en) | 1974-07-11 |
| IT990583B (en) | 1975-07-10 |
| SE411267B (en) | 1979-12-10 |
| JPS4943093A (en) | 1974-04-23 |
| BE799908A (en) | 1973-11-23 |
| NL7307712A (en) | 1973-12-04 |
| JPS5627840B2 (en) | 1981-06-27 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed | ||
| PCNP | Patent ceased through non-payment of renewal fee |