GB1084999A - Improvements in or relating to nuclear reactor fuel elements - Google Patents
Improvements in or relating to nuclear reactor fuel elementsInfo
- Publication number
- GB1084999A GB1084999A GB14420/65A GB1442065A GB1084999A GB 1084999 A GB1084999 A GB 1084999A GB 14420/65 A GB14420/65 A GB 14420/65A GB 1442065 A GB1442065 A GB 1442065A GB 1084999 A GB1084999 A GB 1084999A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- spherical
- mass
- core
- elements
- 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
- 239000003758 nuclear fuel Substances 0.000 title abstract 3
- 239000000446 fuel Substances 0.000 abstract 26
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 abstract 4
- 239000000463 material Substances 0.000 abstract 3
- 230000007246 mechanism Effects 0.000 abstract 3
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 abstract 2
- 239000000919 ceramic Substances 0.000 abstract 2
- 238000005253 cladding Methods 0.000 abstract 2
- 239000002826 coolant Substances 0.000 abstract 2
- 238000000034 method Methods 0.000 abstract 2
- 230000008569 process Effects 0.000 abstract 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 2
- 229910052726 zirconium Inorganic materials 0.000 abstract 2
- FRWYFWZENXDZMU-UHFFFAOYSA-N 2-iodoquinoline Chemical compound C1=CC=CC2=NC(I)=CC=C21 FRWYFWZENXDZMU-UHFFFAOYSA-N 0.000 abstract 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 1
- 239000006096 absorbing agent Substances 0.000 abstract 1
- 239000011358 absorbing material Substances 0.000 abstract 1
- 238000010521 absorption reaction Methods 0.000 abstract 1
- 239000004411 aluminium Substances 0.000 abstract 1
- 229910052782 aluminium Inorganic materials 0.000 abstract 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 abstract 1
- LTPBRCUWZOMYOC-UHFFFAOYSA-N beryllium oxide Inorganic materials O=[Be] LTPBRCUWZOMYOC-UHFFFAOYSA-N 0.000 abstract 1
- 238000009835 boiling Methods 0.000 abstract 1
- 238000010276 construction Methods 0.000 abstract 1
- 238000007796 conventional method Methods 0.000 abstract 1
- 238000009713 electroplating Methods 0.000 abstract 1
- 230000004992 fission Effects 0.000 abstract 1
- 230000004907 flux Effects 0.000 abstract 1
- 239000007789 gas Substances 0.000 abstract 1
- 229910002804 graphite Inorganic materials 0.000 abstract 1
- 239000010439 graphite Substances 0.000 abstract 1
- 150000002500 ions Chemical class 0.000 abstract 1
- 238000005259 measurement Methods 0.000 abstract 1
- 229910052751 metal Inorganic materials 0.000 abstract 1
- 239000002184 metal Substances 0.000 abstract 1
- 230000009257 reactivity Effects 0.000 abstract 1
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 abstract 1
- 229910010271 silicon carbide Inorganic materials 0.000 abstract 1
- 239000007787 solid Substances 0.000 abstract 1
- 229910001220 stainless steel Inorganic materials 0.000 abstract 1
- 239000010935 stainless steel Substances 0.000 abstract 1
Classifications
-
- 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
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
- G21C19/202—Arrangements for handling ball-form, i.e. pebble fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/07—Pebble-bed reactors; Reactors with granular fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/38—Fuel units consisting of a single fuel element in a supporting sleeve or in another supporting element
-
- 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
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,084,999. Reactors. S. WRIGLEY. April 4, 1966 [April 5, 1965], No. 14420/65. Heading G6C. A spherical fuel element comprises a mass of clad nuclear fuel supported within a spherical shell having apertures to allow coolant free access to the clad fuel. The mass of nuclear fuel, which may be spherical and of metallic or ceramic form clad, e.g. in aluminium, zirconium, stainless steel or ceramic, is supported centrally within the spherical shell which may be of graphite, beryllium oxide, silicon carbide or zirconium. Voidage to accommodate fission product gases can be achieved either by using a porous low neutron absorption material as the kernel of the fuel mass or by using a hollow fuel mass. In one embodiment, a solid spherical fuel mass has cladding applied, e.g. by vacuum metallizing process and/or an electroplating process, and is supported in a shell comprising two hemispheres which lock together and which are provided with projections which bear against the clad fuel. In an alternative embodiment, the spherical fuel mass is hollow and has a preformed metal cladding from which radially extend three support wires which are clamped between the two hemispheres forming the shell. Such fuel elements may be used in a boiling heavy water reactor as shown in Fig. 3, the core 1 of which is located within a concrete structure 2 and sub-divided into five zones, a central zone 3 and four radial zones 4. The vertical sides 5 of the core 1 are of unperforated material to assist natural convective water flow, but the bottom 6, top 7 and internal core divisions 8 are of perforated material. Each zone is fitted with a charge mechanism 9 located on a small diameter tower 10 attached to the structure 2 and with a discharge pipe 11. The charge and discharge mechanisms each comprise a plunger 30 having a transverse bore 31 which accommodates one or more fuel elements and to unload fuel elements the bore 31 of a plunger 30 is brought below an outlet from the pressurized core 1 so that fuel elements fall into it. The plunger 30 is then moved to bring the bore 31 into alignment with a discharge orifice through which the fuel elements pass through pipes 11 to a skip 13. When sufficient fuel is in the skip 13 it is hoisted up a tube 15 to the used fuel store 17. All the fuel handling takes place under heavy water and the fuel is always adequately cooled. The fuel passes from the store 17 through one or more grading stations 18 to the graded fuel store 19. New fuel can be introduced by means of an additional station (not shown). From the fuel stations, the fuel is selected according to the fuel cycle and is passed to five stations 20 which feed the five core zones by means of the charging mechanisms 9. Flux measurements can be carried out readily by passing small in-pile ion chambers through small bore tubes of low neutron absorbing material passing through the core. The design of the spherical fuel elements also permits the use of light water/steam as the coolant, the resultant reactor being an epithermal reactor. Neutron absorber in the form of spherical elements of similar construction to the fuel elements but with a neutron absorbing mass in place of the fuel mass can be added to the fuel elements before loading into the core, and the large negative temperature coefficient makes it self-correcting. However, the large negative temperature coefficient dictates a large positive reactivity in the cold condition, and conventional methods of control are needed for start up and for large changes of power.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB14420/65A GB1084999A (en) | 1965-04-05 | 1965-04-05 | Improvements in or relating to nuclear reactor fuel elements |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB14420/65A GB1084999A (en) | 1965-04-05 | 1965-04-05 | Improvements in or relating to nuclear reactor fuel elements |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1084999A true GB1084999A (en) | 1967-09-27 |
Family
ID=10040903
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB14420/65A Expired GB1084999A (en) | 1965-04-05 | 1965-04-05 | Improvements in or relating to nuclear reactor fuel elements |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1084999A (en) |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4092217A (en) * | 1973-03-30 | 1978-05-30 | Hochtemperatur-Kernkraftwerk Gmbh (Hkg) Gemeinsames Europaisches Unternehman | Fuel elements for nuclear reactors and method for testing the circulation of fuel elements in a core of a nuclear reactor |
US4274920A (en) * | 1977-04-13 | 1981-06-23 | Gibbs & Hill, Inc. | Water-cooled nuclear reactor with passive emergency shutdown and core cooling capability and on-line refueling |
US4695423A (en) * | 1985-09-18 | 1987-09-22 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Method for loading, operating, and unloading a ball-bed nuclear reactor |
US4789519A (en) * | 1983-09-30 | 1988-12-06 | Hochtemperatur-Reaktorbau Gmbh | Nuclear reactor plant |
WO2007030224A3 (en) * | 2005-07-27 | 2007-05-31 | Battelle Memorial Institute | A proliferation-resistant nuclear reactor |
WO2014015740A1 (en) * | 2012-07-25 | 2014-01-30 | Li Zhengwei | Spherical fuel reactor |
-
1965
- 1965-04-05 GB GB14420/65A patent/GB1084999A/en not_active Expired
Cited By (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4092217A (en) * | 1973-03-30 | 1978-05-30 | Hochtemperatur-Kernkraftwerk Gmbh (Hkg) Gemeinsames Europaisches Unternehman | Fuel elements for nuclear reactors and method for testing the circulation of fuel elements in a core of a nuclear reactor |
US4274920A (en) * | 1977-04-13 | 1981-06-23 | Gibbs & Hill, Inc. | Water-cooled nuclear reactor with passive emergency shutdown and core cooling capability and on-line refueling |
US4789519A (en) * | 1983-09-30 | 1988-12-06 | Hochtemperatur-Reaktorbau Gmbh | Nuclear reactor plant |
US4695423A (en) * | 1985-09-18 | 1987-09-22 | Kernforschungsanlage Julich Gesellschaft Mit Beschrankter Haftung | Method for loading, operating, and unloading a ball-bed nuclear reactor |
WO2007030224A3 (en) * | 2005-07-27 | 2007-05-31 | Battelle Memorial Institute | A proliferation-resistant nuclear reactor |
WO2014015740A1 (en) * | 2012-07-25 | 2014-01-30 | Li Zhengwei | Spherical fuel reactor |
CN103578575A (en) * | 2012-07-25 | 2014-02-12 | 李正蔚 | Spherical fuel reactor |
GB2518991A (en) * | 2012-07-25 | 2015-04-08 | Zhengwei Li | Spherical fuel reactor |
JP2015527575A (en) * | 2012-07-25 | 2015-09-17 | 李正蔚 | Spherical fuel reactor |
EP2879133A4 (en) * | 2012-07-25 | 2016-03-16 | Zhengwei Li | SPHERICAL FUEL REACTOR |
CN103578575B (en) * | 2012-07-25 | 2016-08-31 | 李正蔚 | Pebble-bed reactor |
GB2518991B (en) * | 2012-07-25 | 2018-06-06 | Li Zhengwei | Spherical fuel reactor |
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