GB1253569A - Nuclear reactors - Google Patents
Nuclear reactorsInfo
- Publication number
- GB1253569A GB1253569A GB22627/69A GB2262769A GB1253569A GB 1253569 A GB1253569 A GB 1253569A GB 22627/69 A GB22627/69 A GB 22627/69A GB 2262769 A GB2262769 A GB 2262769A GB 1253569 A GB1253569 A GB 1253569A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- elements
- fuel elements
- core
- grid
- 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
- 239000000446 fuel Substances 0.000 abstract 23
- 229910000831 Steel Inorganic materials 0.000 abstract 3
- 230000001105 regulatory effect Effects 0.000 abstract 3
- 239000010959 steel Substances 0.000 abstract 3
- 238000001816 cooling Methods 0.000 abstract 2
- 239000012634 fragment Substances 0.000 abstract 2
- 238000009825 accumulation Methods 0.000 abstract 1
- 238000010276 construction Methods 0.000 abstract 1
- 239000002826 coolant Substances 0.000 abstract 1
- 239000000463 material Substances 0.000 abstract 1
- 239000011513 prestressed concrete Substances 0.000 abstract 1
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
-
- 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
- G21C1/028—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a pressurised coolant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/10—Lifting devices or pulling devices adapted for co-operation with fuel elements or with control elements
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1,253,569. Reactors. SIEMENS A.G. 2 May, 1969 [3 May, 1968], No. 22627/69. Heading G6C. A reactor core includes an array of rod-like fuel elements suspended from their upper ends to hang downwardly alongside one another from a support grid, the upper ends being arranged within a single cell of the grid in a manner enabling the elements to be removed upwardly for replacement through the grid, and the elements being bounded by flat lateral surfaces by virtue of which they fit closely together in the array. A gas-cooled, fast breeder reactor is described in which the core is situated in the upper part of a prestressed concrete pressure vessel closed at its upper end by a cover plate 102, a steam generator being located in the lower part of the pressure vessel. The core includes fuel elements suspended from a support grid 10, which in turn is secured by means of tie-rods to the cover plate 102. The fuel elements, which each contain a plurality of fuel or breeder material rods, are of generally square cross-section and arranged in sets of nine, with a central element 9 laterally enclosed by elements 1 to 8. The enclosing fuel elements 1 to 8 are narrowed along upper portions, the length of which approximately equals the height of the grid 10, on two adjacent lateral sides 12, 13. At the upper ends of these sides, the elements are provided with projecting support hooks 14, 15 and 16 for engagement with the support grid 10. In contrast, the enclosed fuel element 9 has a uniform square cross-section along its entire length. Provided at the upper end of this fuel element 9 are projecting support fillets 21 which bear against bevelled portions of the fuel elements 1 to 8. The fuel element 9 is formed with a longitudinal bore inside which is located a regulating rod 20. In order to avoid unwanted stressing of the tubular casings of the fuel rods inside the elements, gas is supplied to the interior of the fuel rods through pipes 17. Regulating valves 22 are provided at the upper ends of the fuel elements for regulation of the throughput of coolant through the fuel elements. A plug (not shown) in an aperture in the cover plate 102 and thermal shield 107 has a hollow cylindrical extension by means of which the fuel elements 1 to 8 are held down in position. Drive means for the regulating rod 20 are provided in the plug. A loading machine (not shown) travels over the cover plate on a co-ordinate chassis, so that each point can be reached. The plug is released and drawn into the loading machine and a holding-down tube 29 introduced into the aperture 23. The tube 29 has at its lower end a lateral aperture 30 extending around a quarter of its periphery, and the tube 29 and a manipulating rod 31 are rotatable by means of a drive in steps of 45 degrees so that a gripping head 32, which is displaceable through the aperture 30, can reach all the elements of the array which are suspended around the fuel element 9. The tube 29 holds the fuel elements 1 to 8 down against the grid 10 while the fuel element 9 is withdrawn. The fuel element 9 is engaged by pawls of the gripping head 32 and is drawn upwards into the loading machine with the aid of the manipulating rod 31. The loading machine has its own gas cooling system for cooling the spent fuel elements. Once the fuel element 9 has been removed, the fuel elements 1 to 8 are gripped by the gripping head 32, lifted to a small extent so that they are unhooked from the support grid 10, and then guided inwardly under the aperture in the cover plate 102, so that they can then be withdrawn into the loading machine. A net-like steel structure may be so disposed below the core that, in the event of inadvertent incorrect loading of the core with fuel elements, individual fuel elements are prevented from falling down on to the distributer cone disposed beneath the core. However, in case the whole core should break up, and a large number of fuel elements fall from the support grid, or the core melt and many fragments fall, the steel structure should be of such weak construction as to yield and permit the fallen elements or fragments to fall on to the distributer cone and thereby prevent accumulation on the steel structure of a critical mass.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE1764258A DE1764258C3 (en) | 1968-05-03 | 1968-05-03 | Nuclear reactor with gas cooling |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1253569A true GB1253569A (en) | 1971-11-17 |
Family
ID=5697915
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB22627/69A Expired GB1253569A (en) | 1968-05-03 | 1969-05-02 | Nuclear reactors |
Country Status (2)
Country | Link |
---|---|
DE (1) | DE1764258C3 (en) |
GB (1) | GB1253569A (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB1472477A (en) * | 1974-05-10 | 1977-05-04 | Nuclear Power Co Ltd | Nuclear reactor installations |
-
1968
- 1968-05-03 DE DE1764258A patent/DE1764258C3/en not_active Expired
-
1969
- 1969-05-02 GB GB22627/69A patent/GB1253569A/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
DE1764258B2 (en) | 1973-08-30 |
DE1764258C3 (en) | 1974-05-02 |
DE1764258A1 (en) | 1972-01-27 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB871897A (en) | Nuclear reactor | |
US2992174A (en) | Breeder-converter reactor | |
ES8105881A1 (en) | Fuel assembly for a boiling nuclear reactor | |
DE3566752D1 (en) | Submoderated nuclear reactor | |
GB847843A (en) | Engineering test nuclear reactor | |
US4111747A (en) | Packed rod neutron shield for fast nuclear reactors | |
US3179571A (en) | Nuclear fuel units with enclosures of the thimble type for pressure-tube nuclear reactors | |
GB931972A (en) | Reflector for nuclear reactors | |
GB1458690A (en) | Nuclear reactor internals arrangement | |
GB1253569A (en) | Nuclear reactors | |
GB867454A (en) | Gas-cooled neutronic reactor | |
US3652394A (en) | Device for controlling the reactivity of nuclear reactors | |
US3227620A (en) | Gas cooled nuclear reactor having removable fuel tube assemblies disposed in mass of granular moderator | |
US4086133A (en) | Nuclear reactor core refueling method | |
US4704247A (en) | Method and apparatus for compacting spent nuclear reactor fuel rods | |
US4022661A (en) | Fuel rod support means | |
US4775507A (en) | Method for compacting spent nuclear reactor fuel rods | |
GB913653A (en) | Improvements in or relating to nuclear reactors | |
DE1038665B (en) | Loading and unloading device for a reactor operated with high cooling gas pressure | |
GB1084999A (en) | Improvements in or relating to nuclear reactor fuel elements | |
US3163584A (en) | Support housing for externally supporting fuel elements | |
GB962311A (en) | Improvements in or relating to liquid moderated nuclear reactors | |
US4070241A (en) | Nuclear reactor removable radial shielding assembly having a self-bowing feature | |
GB984193A (en) | Improvements in or relating to nuclear reactors | |
US5180540A (en) | Fuel rod consolidation structure |