GB1248174A - A safeguard for a nuclear reactor - Google Patents
A safeguard for a nuclear reactorInfo
- Publication number
- GB1248174A GB1248174A GB01396/70A GB1139670A GB1248174A GB 1248174 A GB1248174 A GB 1248174A GB 01396/70 A GB01396/70 A GB 01396/70A GB 1139670 A GB1139670 A GB 1139670A GB 1248174 A GB1248174 A GB 1248174A
- Authority
- GB
- United Kingdom
- Prior art keywords
- reservoir
- tube
- reactor
- liquid
- duct
- 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
- 239000007788 liquid Substances 0.000 abstract 6
- 239000002574 poison Substances 0.000 abstract 3
- 231100000614 poison Toxicity 0.000 abstract 3
- 239000007789 gas Substances 0.000 abstract 2
- 230000015572 biosynthetic process Effects 0.000 abstract 1
- 239000001307 helium Substances 0.000 abstract 1
- 229910052734 helium Inorganic materials 0.000 abstract 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 abstract 1
- 239000011261 inert gas Substances 0.000 abstract 1
- 239000000463 material Substances 0.000 abstract 1
- 239000007787 solid Substances 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-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
- G21C9/033—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 an absorbent fluid
-
- 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
- G21C7/22—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 a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
-
- 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)
Abstract
1,248,174. Controlling reactors. COMMISSARIAT A L'ENERGIE ATOMIQUE. 10 March, 1970 [19 March, 1969], No. 11396/70. Heading G6C. A liquid poison safeguard for a nuclear reactor comprises a reservoir 4 adapted to contain liquid poison, e.g. boronated water, and housed within a wall 1 secured between the reactor pressure vessel 2 and a biological shielding slab 3. The reservoir 4 is closed by a plug 6 which can be either solid or filled with a shielding material 7. A tube 8 closed at its lower end like a glove finger extends from the reservoir 4 down through the pressure vessel 2 and is guided on the bottom of the vessel 2 in a funnel 10. Extending axially through the reservoir 4 is a duct 12 whose bottom orifice 13 communicates with the top of the tube 8 near the bottom of the reservoir 4. Tube 8 bears a large diameter cylindrical skirt 14 which is disposed around an inverted cone 16 to form a siphon 15 which serves to retain the liquid poison in the reservoir 4. In normal reactor operation, the tube 8 is filled with an inert gas, e.g. helium, the pressure of which is adjusted by a compressor 24. The pressure in the tube 8 normally balances that of the liquid in the reservoir 4 but if the pressure in the tube 8 drops, the liquid escapes from the reservoir through the siphon 15 and fills the tube 8. Fins 42 are disposed around duct 12 to impart a whirling motion to the liquid and to assit in the formation at the centre of tube 8 of a passage through which the gas can pass to the duct 12. The duet 12 can be extended for some distance inside tube 8 by an extension 33 pierced by a number of orifices or formed by a tubular latticework. Valves 22 are opened and the gas passes through duct 26 to the reservoir 4. A drain tube 28 extends from the bottom of tube 8 between the well 1 and the reservoir 4 and is connected outside the reactor to a pump 30, valve 34 and return line 32. The pump 30 is operated after valve 34 has been opened to restart the reactor. The reservoir 4 is releasably secured to the wall 1 by screws 44. In alternative embodiments, the siphon is replaced by a valve operated from outside the reactor (Fig. 2, not shown) and the reservoir is mounted directly on the pressure vessel wall (Fig. 3, not shown).
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR6907829A FR2038062A1 (en) | 1969-03-19 | 1969-03-19 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1248174A true GB1248174A (en) | 1971-09-29 |
Family
ID=9030867
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB01396/70A Expired GB1248174A (en) | 1969-03-19 | 1970-03-10 | A safeguard for a nuclear reactor |
Country Status (4)
| Country | Link |
|---|---|
| BE (1) | BE747032A (en) |
| DE (1) | DE7010049U (en) |
| FR (1) | FR2038062A1 (en) |
| GB (1) | GB1248174A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2024125840A1 (en) * | 2022-12-12 | 2024-06-20 | Moltex Energy Ltd | Temperature activated passive shutdown device for a nuclear reactor |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2188247B1 (en) * | 1972-06-02 | 1974-10-25 | Activite Atom Avance | |
| US4371495A (en) * | 1981-01-23 | 1983-02-01 | Westinghouse Electric Corp. | Self rupturing gas moderator rod for a nuclear reactor |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1125562B (en) * | 1958-04-03 | 1962-03-15 | Rhein Westfael Elect Werk Ag | Device for regulating nuclear reactors |
| GB882361A (en) * | 1958-11-14 | 1961-11-15 | Thompson Nuclear Energy Co Ltd | Improvements relating to control means for nuclear reactors |
| BE635474A (en) * | 1962-07-27 | 1900-01-01 |
-
1969
- 1969-03-19 FR FR6907829A patent/FR2038062A1/fr not_active Withdrawn
-
1970
- 1970-03-09 BE BE747032D patent/BE747032A/en unknown
- 1970-03-10 GB GB01396/70A patent/GB1248174A/en not_active Expired
- 1970-03-18 DE DE7010049U patent/DE7010049U/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2024125840A1 (en) * | 2022-12-12 | 2024-06-20 | Moltex Energy Ltd | Temperature activated passive shutdown device for a nuclear reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| DE7010049U (en) | 1970-06-25 |
| BE747032A (en) | 1970-08-17 |
| FR2038062A1 (en) | 1971-01-08 |
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