GB1249331A - Improvements in or relating to liquid metal cooled fast breeder nuclear reactors - Google Patents
Improvements in or relating to liquid metal cooled fast breeder nuclear reactorsInfo
- Publication number
- GB1249331A GB1249331A GB8535/68A GB853568A GB1249331A GB 1249331 A GB1249331 A GB 1249331A GB 8535/68 A GB8535/68 A GB 8535/68A GB 853568 A GB853568 A GB 853568A GB 1249331 A GB1249331 A GB 1249331A
- Authority
- GB
- United Kingdom
- Prior art keywords
- shield
- sodium
- core
- ducts
- fuel
- 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
- 229910001338 liquidmetal Inorganic materials 0.000 title 1
- 239000000446 fuel Substances 0.000 abstract 8
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract 7
- 229910052708 sodium Inorganic materials 0.000 abstract 7
- 239000011734 sodium Substances 0.000 abstract 7
- 239000002826 coolant Substances 0.000 abstract 5
- 238000000429 assembly Methods 0.000 abstract 4
- 238000009413 insulation Methods 0.000 abstract 2
- 238000012986 modification Methods 0.000 abstract 1
- 230000004048 modification Effects 0.000 abstract 1
Classifications
-
- 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
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,249,331. Fast reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 9 Jan., 1969 [30 Jan., 1968; 21 Feb., 1968], Nos. 4847/68 and 8535/68. Heading G6C. A large power-producing fast breeder reactor comprises a sodium-filled tank 1 within a vault 2 closed by a roof 3. The sodium level is denoted by chain-line L and disposed in the sodium are the reactor core 4, four primary heat exchangers 6, four sodium-coolant pumps 7 and interconnecting ducts 15, 16, 17. The core 4 is disposed in an open-topped vessel 50 having thermal insulation 9 and neutron shielding 10 and closed by a lid 11 having neutron shielding 22. A platform 12 constituting the bottom of the vessel 50 is supported by beams 13 suspended by a cylinder 14 from the roof 3, the lid 11 being suspended by a pillar 44. The ducts 15 penetrate the side wall 8 of the vessel 50 and conduct hot coolant from the upper region of the core to the heat exchangers 6. The ducts 16 lead the coolant from the exchangers 6, to the inlet of pumps 7, the coolant being returned to the lower end of the core by the ducts 17. The ducts 17 extend through platform 12 and terminate at a junction with the inlet ends of fuel element support tubes (not shown) carried by the diagrid 18. Leakage or flow-back of sodium from the junction mentioned above collects in a tank 20 and is returned by ducts 21 to a pump 7. Additionally, (not shown) the ducts 21 can be branched to the upper end of the core to scavenge cool sodium from the sodium pool in the tank which may otherwise be able to leak through the lid 11. A fuel store 24 for irradiated fuel sub-assemblies 27 has thermal insulation 26 and is disposed adjacent the vessel 50, these subassemblies being cooled by convection flow of sodium in the pool. The fuel sub-assemblies are transferred from the core 4 to the store 24 by tubes 23 provided at their upper ends with transfer machines (not shown), the upper ends of the pipes terminating in a rotatable inner shield 32. The inner shield 32 is eccentrically mounted in an outer rotatable shield 33 and the axis of the shield 32 may be aligned with the axis of the core 4. A refuelling machine 31 on the outer shield 33 may be connected at its upper end to a flask (not shown) whereby new fuel sub-assemblies may be loaded into the store 24 and irradiated fuel sub-assemblies may be removed to a remote facility. The inner shield 32 also supports the lid 11 through the pillar 44 and carries equipment 36 for operating the control elements 37. Further equipment 41, 42 43 carried by the shield 32 serves to monitor the coolant and measure the fuel temperature. Jacking means (not shown) are provided for lifting the shield 32 relatively to the shield 33 prior to rotation of the shield 32 or 33. In a modification described with reference to Figs. 3-5 (not shown) the tank 1 is elliptical in plan view, the reactor core being situated at the centre of the major axis but displaced off-centre on the minor axis to provide space for the fuel store. The space at each end of the ellipse is occupied by the primary heat exchangers and pumps.
Priority Applications (7)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US00790779A US3715270A (en) | 1968-01-30 | 1969-01-13 | Nuclear reactors |
DE1904200A DE1904200C3 (en) | 1968-01-30 | 1969-01-29 | Fast power breeder reactor cooled with liquid metal |
FR696901789A FR2000967B1 (en) | 1968-01-30 | 1969-01-29 | |
SE01188/69A SE350139B (en) | 1968-01-30 | 1969-01-29 | |
JP44006587A JPS4840280B1 (en) | 1968-01-30 | 1969-01-29 | |
ES363057A ES363057A1 (en) | 1968-01-30 | 1969-01-29 | Nuclear reactors |
BE727691D BE727691A (en) | 1968-01-30 | 1969-01-30 |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB484768 | 1968-01-30 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1249331A true GB1249331A (en) | 1971-10-13 |
Family
ID=9784919
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB8535/68A Expired GB1249331A (en) | 1968-01-30 | 1968-01-30 | Improvements in or relating to liquid metal cooled fast breeder nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1249331A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4331512A (en) * | 1979-04-23 | 1982-05-25 | Electric Power Research Institute, Inc. | Nuclear reactor guard vessel arrangement |
US4336614A (en) * | 1978-09-19 | 1982-06-22 | Nuclear Power Company Limited | Tube-in-shell heat exchangers |
CN113130096A (en) * | 2021-03-05 | 2021-07-16 | 安徽中科超核科技有限公司 | Liquid metal reactor for vehicle-mounted transportation |
CN116052909A (en) * | 2022-12-26 | 2023-05-02 | 中国原子能科学研究院 | Reactor vessel |
-
1968
- 1968-01-30 GB GB8535/68A patent/GB1249331A/en not_active Expired
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4336614A (en) * | 1978-09-19 | 1982-06-22 | Nuclear Power Company Limited | Tube-in-shell heat exchangers |
US4331512A (en) * | 1979-04-23 | 1982-05-25 | Electric Power Research Institute, Inc. | Nuclear reactor guard vessel arrangement |
CN113130096A (en) * | 2021-03-05 | 2021-07-16 | 安徽中科超核科技有限公司 | Liquid metal reactor for vehicle-mounted transportation |
CN113130096B (en) * | 2021-03-05 | 2022-07-19 | 安徽中科超核科技有限公司 | Liquid metal reactor for vehicle-mounted transportation |
CN116052909A (en) * | 2022-12-26 | 2023-05-02 | 中国原子能科学研究院 | Reactor vessel |
CN116052909B (en) * | 2022-12-26 | 2023-10-27 | 中国原子能科学研究院 | Reactor vessel |
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