ES236651A1 - Un procedimiento de fabricaciën de productos ceramicos a base de biëxido de uranio para nucleos de elementos combustibles de reactores nucleares - Google Patents
Un procedimiento de fabricaciën de productos ceramicos a base de biëxido de uranio para nucleos de elementos combustibles de reactores nuclearesInfo
- Publication number
- ES236651A1 ES236651A1 ES0236651A ES236651A ES236651A1 ES 236651 A1 ES236651 A1 ES 236651A1 ES 0236651 A ES0236651 A ES 0236651A ES 236651 A ES236651 A ES 236651A ES 236651 A1 ES236651 A1 ES 236651A1
- Authority
- ES
- Spain
- Prior art keywords
- translation
- machine
- legally binding
- google translate
- uranium
- 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
Classifications
-
- 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
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Procedimiento de fabricación de productos cerámicos a base de bióxido de uranio para núcleos de elementos combustibles de reactores nucleares, caracterizado por someter el bióxido de uranio ( UO 2) a una molienda mecánica seca, hasta obtener un polvo fino del que se empleará, para las operaciones siguientes, mezclas constituída por fracciones granulométricas con un 25 por 100 de finos, inferiores a 5 micras, otro 25 por 100 superiores a 10 micras, desecándose las fracciones superiores a 20 micras. Previa la separación granulométrica se hará una separación magnética del metal.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
ES0236651A ES236651A1 (es) | 1957-07-19 | 1957-07-19 | Un procedimiento de fabricaciën de productos ceramicos a base de biëxido de uranio para nucleos de elementos combustibles de reactores nucleares |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
ES0236651A ES236651A1 (es) | 1957-07-19 | 1957-07-19 | Un procedimiento de fabricaciën de productos ceramicos a base de biëxido de uranio para nucleos de elementos combustibles de reactores nucleares |
Publications (1)
Publication Number | Publication Date |
---|---|
ES236651A1 true ES236651A1 (es) | 1958-06-01 |
Family
ID=34444702
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES0236651A Expired ES236651A1 (es) | 1957-07-19 | 1957-07-19 | Un procedimiento de fabricaciën de productos ceramicos a base de biëxido de uranio para nucleos de elementos combustibles de reactores nucleares |
Country Status (1)
Country | Link |
---|---|
ES (1) | ES236651A1 (es) |
-
1957
- 1957-07-19 ES ES0236651A patent/ES236651A1/es not_active Expired
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB850016A (en) | Improvements in or relating to methods of manufacturing graphite bodies and nuclear fuel materials comprising said graphite bodies | |
CA946164A (en) | Process for separation of protactinium, thorium and uranium from neutron-irradiated thorium | |
ES236651A1 (es) | Un procedimiento de fabricaciën de productos ceramicos a base de biëxido de uranio para nucleos de elementos combustibles de reactores nucleares | |
ES270240A1 (es) | Procedimiento de obtención de material combustible cerámico para reactores nucleares | |
ES299210A1 (es) | Método de preparación de elementos combustibles nucleares | |
GB801288A (en) | Fuel for nuclear reactors and process of making the same | |
GB821297A (en) | Homogeneous fuel elements for nuclear fission reactors | |
AU216706B2 (en) | Fuel for neutronic reactors and process of making | |
CA587215A (en) | Process for the preparation of coke with highly moderating properties and for the use thereof in nuclear reactors | |
CA587214A (en) | Fuel for neutronic reactors and process of making | |
AU2219156A (en) | Fuel for neutronic reactors and process of making | |
Dunnington | Effect of Irradiation on Uranium | |
AU219754B2 (en) | Improvements relating to fuel elements for nuclear reactors and to nuclear reactors using such elements | |
AU223047B2 (en) | Improvements in nuclear reactors andin or relating to nuclear reactor fuel elements | |
ES356479A1 (es) | Un procedimiento perfeccionado para producir cerametales dedioxido de uranio-columbio de ductilidad aumentada ycargas de uo2. | |
GB898849A (en) | Improvements in or relating to fuel elements for nuclear reactors | |
CA605728A (en) | Sintered nuclear reactor fuel bodies and method of making them | |
AU216429B2 (en) | Improvements in or relating to fuel elements for nuclear reactors | |
AU223770B2 (en) | Improvements in and relating to fuel elements for nuclear reactors | |
AU220648B2 (en) | Improvements in and relating to fuel elements for nuclear reactors | |
AU227468B2 (en) | Method of producing uranium metal | |
AU159720B2 (en) | Improvements in or relating to nuclear fuel rods in apparatus for neutron irradiation of materials | |
AU209972B2 (en) | Improvements in nuclear reactor fuel elements | |
AU3070057A (en) | Improvements in nuclear reactors andin or relating to nuclear reactor fuel elements | |
AU222123B2 (en) | Improvements in or relating to removal of fission products from nuclear reactors |