GB1397014A - Fabrication process for nuclear fuel pellets - Google Patents
Fabrication process for nuclear fuel pelletsInfo
- Publication number
- GB1397014A GB1397014A GB1727773A GB1727773A GB1397014A GB 1397014 A GB1397014 A GB 1397014A GB 1727773 A GB1727773 A GB 1727773A GB 1727773 A GB1727773 A GB 1727773A GB 1397014 A GB1397014 A GB 1397014A
- Authority
- GB
- United Kingdom
- Prior art keywords
- pellets
- compression moulded
- pellet
- binder
- nuclear 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
- 239000008188 pellet Substances 0.000 title abstract 11
- 239000003758 nuclear fuel Substances 0.000 title abstract 3
- 238000004519 manufacturing process Methods 0.000 title 1
- 238000000034 method Methods 0.000 title 1
- 230000006835 compression Effects 0.000 abstract 5
- 238000007906 compression Methods 0.000 abstract 5
- 239000011230 binding agent Substances 0.000 abstract 3
- 238000001125 extrusion Methods 0.000 abstract 2
- 239000000446 fuel Substances 0.000 abstract 2
- 238000005245 sintering Methods 0.000 abstract 2
- 239000007787 solid Substances 0.000 abstract 2
- DSSYKIVIOFKYAU-XCBNKYQSSA-N (R)-camphor Chemical compound C1C[C@@]2(C)C(=O)C[C@@H]1C2(C)C DSSYKIVIOFKYAU-XCBNKYQSSA-N 0.000 abstract 1
- 241000723346 Cinnamomum camphora Species 0.000 abstract 1
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 abstract 1
- 229960000846 camphor Drugs 0.000 abstract 1
- 229930008380 camphor Natural products 0.000 abstract 1
- 238000001035 drying Methods 0.000 abstract 1
- 229910052739 hydrogen Inorganic materials 0.000 abstract 1
- 239000001257 hydrogen Substances 0.000 abstract 1
- 239000000203 mixture Substances 0.000 abstract 1
- 238000000465 moulding Methods 0.000 abstract 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B35/00—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
- C04B35/622—Forming processes; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
- C04B35/626—Preparing or treating the powders individually or as batches ; preparing or treating macroscopic reinforcing agents for ceramic products, e.g. fibres; mechanical aspects section B
- C04B35/63—Preparing or treating the powders individually or as batches ; preparing or treating macroscopic reinforcing agents for ceramic products, e.g. fibres; mechanical aspects section B using additives specially adapted for forming the products, e.g.. binder binders
- C04B35/632—Organic additives
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B35/00—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
- C04B35/51—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on compounds of actinides
-
- 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/623—Oxide fuels
-
- 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
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Physics & Mathematics (AREA)
- Manufacturing & Machinery (AREA)
- Structural Engineering (AREA)
- Materials Engineering (AREA)
- Organic Chemistry (AREA)
- Plasma & Fusion (AREA)
- Inorganic Chemistry (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
Abstract
1397014 Moulding nuclear fuel pellets AUSTRALIAN ATOMIC ENERGY COMMISSION 10 April 1973 [13 April 1972] 17277/73 Heading B5A [Also in Division G6] A nuclear fuel pellet is produced by extruding a mixture of powdered fuel and binder which is cut at the extruder die into pellets and, after drying, one or more juxtaposed pellets are compression moulded within a die of larger area, and at a pressure greater than that of extrusion, and the compression moulded pellet is sintered. Reject extruded pellets may be recycled to the extruder. The fuel may comprise natural or enriched UO 2 , or PuO 2 , or UO 2 -PuO 2 . The binder may compise camphor, when the sintering is effected in hydrogen or, with a less easily removable binder, debonding may be effected prior to sintering. The extrusion and compression moulded pellets may be of cylindrical solid, or tubular section, and the compression moulded pellet may comprise regions of different fissile content, as in the Fig. 4c embodiment wherein a compression moulded pellet is moulded from extruded pellets 18, 17 of solid and tubular section, between opposed plungers 19, 21.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
AUPA859372 | 1972-04-13 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1397014A true GB1397014A (en) | 1975-06-11 |
Family
ID=3764988
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1727773A Expired GB1397014A (en) | 1972-04-13 | 1973-04-10 | Fabrication process for nuclear fuel pellets |
Country Status (2)
Country | Link |
---|---|
CA (1) | CA1009434A (en) |
GB (1) | GB1397014A (en) |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2379885A1 (en) * | 1977-02-04 | 1978-09-01 | Westinghouse Electric Corp | ARRANGEMENT FOR THE MANUFACTURE OF NUCLEAR FUEL PELLETS |
DE2816141A1 (en) * | 1977-04-29 | 1978-11-02 | Westinghouse Electric Corp | TEST DEVICE FOR NUCLEAR FUEL TABLETS |
FR2506497A1 (en) * | 1981-05-19 | 1982-11-26 | British Nuclear Fuels Ltd | PROCESS FOR MANUFACTURING NUCLEAR FUEL PELLETS AND PELLET THUS FORMED |
GB2127735A (en) * | 1982-07-21 | 1984-04-18 | Atomic Energy Authority Uk | Extruding loose (particulate) material into coherent bodies |
EP0840330A1 (en) * | 1996-11-01 | 1998-05-06 | General Electric Company | Segmented pellet and production thereof |
US5916497A (en) * | 1994-12-16 | 1999-06-29 | British Nuclear Fuels Plc | Manufacturing of ceramic articles |
WO2000045394A1 (en) * | 1999-01-26 | 2000-08-03 | Belgonucleaire Sa | Method for dry process recycling of mixed (u, pu)o2 oxide nuclear fuel waste |
-
1973
- 1973-04-10 GB GB1727773A patent/GB1397014A/en not_active Expired
- 1973-04-11 CA CA168,494A patent/CA1009434A/en not_active Expired
Cited By (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2379885A1 (en) * | 1977-02-04 | 1978-09-01 | Westinghouse Electric Corp | ARRANGEMENT FOR THE MANUFACTURE OF NUCLEAR FUEL PELLETS |
DE2816141A1 (en) * | 1977-04-29 | 1978-11-02 | Westinghouse Electric Corp | TEST DEVICE FOR NUCLEAR FUEL TABLETS |
FR2506497A1 (en) * | 1981-05-19 | 1982-11-26 | British Nuclear Fuels Ltd | PROCESS FOR MANUFACTURING NUCLEAR FUEL PELLETS AND PELLET THUS FORMED |
GB2127735A (en) * | 1982-07-21 | 1984-04-18 | Atomic Energy Authority Uk | Extruding loose (particulate) material into coherent bodies |
US5916497A (en) * | 1994-12-16 | 1999-06-29 | British Nuclear Fuels Plc | Manufacturing of ceramic articles |
EP0840330A1 (en) * | 1996-11-01 | 1998-05-06 | General Electric Company | Segmented pellet and production thereof |
WO2000045394A1 (en) * | 1999-01-26 | 2000-08-03 | Belgonucleaire Sa | Method for dry process recycling of mixed (u, pu)o2 oxide nuclear fuel waste |
US6783706B1 (en) | 1999-01-26 | 2004-08-31 | Belgonucleaire Sa | Method for dry process recycling of mixed (U,Pu)O2 oxide nuclear fuel waste |
Also Published As
Publication number | Publication date |
---|---|
CA1009434A (en) | 1977-05-03 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
DE1187744B (en) | A fuel element designed for a boiler reactor with a neutron moderating coolant | |
ES350364A1 (en) | Process for manufacturing sintered pellets of nuclear fuel | |
GB1397014A (en) | Fabrication process for nuclear fuel pellets | |
DE2401293C2 (en) | ||
ES419677A1 (en) | Process for controlling end-point density of sintered uranium dioxide nuclear fuel bodies and product | |
GB1375498A (en) | ||
ES473401A1 (en) | Method of producing PuO2/UO2/-nuclear fuels | |
GB1219472A (en) | Method of fabrication of porous bodies of alumina | |
US3992494A (en) | Method of making an oxide fuel compact | |
GB1062247A (en) | Long lifetime nuclear reactor | |
SE7904201L (en) | PREPARATION OF CURRENCY PELLETS | |
JPS529792A (en) | Fuel assembly | |
GB982926A (en) | Coherent nuclear materials and reactor elements made therefrom | |
KR20110089801A (en) | Uranium dioxide fuel pellet including ni oxide and al oxide and the manufacturing method thereof | |
GB1371595A (en) | Manufacturing process for mixed nuclear fuel pellets | |
DE1215266B (en) | Process for the production of a nuclear fuel body from plutonium oxide, thorium oxide, uranium oxide or mixtures of these oxides | |
DE3433416A1 (en) | METHOD FOR PRODUCING FUEL PELLETS FOR A CORE REACTOR | |
DE3218779A1 (en) | Production of fuel pellets for nuclear fuel elements | |
KR101535173B1 (en) | The method for fabrication of oxide fuel pellets and the oxide fuel pellets thereby | |
JPS6479691A (en) | Manufacture of mox fuel | |
JPS5442588A (en) | Fuel assembly | |
JPS5352900A (en) | Fuel rod | |
CH396238A (en) | Process for the production of nuclear fuel and apparatus for carrying out the process | |
GB1191946A (en) | Manufacture of Heat and Erosion Resistant Parts | |
GB1320792A (en) | Method of manufacturing sintered non-stoichiometric oxides |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |