ES8507287A1 - Metodo para tratar residuo de combustible nuclear a base de uo2. - Google Patents
Metodo para tratar residuo de combustible nuclear a base de uo2.Info
- Publication number
- ES8507287A1 ES8507287A1 ES519079A ES519079A ES8507287A1 ES 8507287 A1 ES8507287 A1 ES 8507287A1 ES 519079 A ES519079 A ES 519079A ES 519079 A ES519079 A ES 519079A ES 8507287 A1 ES8507287 A1 ES 8507287A1
- Authority
- ES
- Spain
- Prior art keywords
- gas
- column
- nuclear fuel
- scrap
- treating nuclear
- 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
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
- B01J8/00—Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes
- B01J8/18—Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles
- B01J8/24—Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles according to "fluidised-bed" technique
- B01J8/40—Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles according to "fluidised-bed" technique with fluidised bed subjected to vibrations or pulsations
-
- 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
- G21C19/42—Reprocessing of irradiated fuel
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/01—Oxides; Hydroxides
- C01G43/025—Uranium dioxide
-
- 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
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
- C01P2006/00—Physical properties of inorganic compounds
- C01P2006/80—Compositional purity
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/22—Devices for withdrawing samples in the gaseous state
-
- 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)
- Physics & Mathematics (AREA)
- Organic Chemistry (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- Combustion & Propulsion (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Ceramic Engineering (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Processing Of Solid Wastes (AREA)
- Fluidized-Bed Combustion And Resonant Combustion (AREA)
- Solid Fuels And Fuel-Associated Substances (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Abstract
METODO PARA TRATAR RESIDUO DE COMBUSTIBLE NUCLEAR A BASE DE UO2.CONSISTE EN: OXIDAR EL RESIDUO DE COMBUSTIBLE NUCLEAR A BASE DE UO2 EN ESTADO FLUIDIZADO, EN UN PRIMER LUGAR EN UN GAS OXIDANTE QUE TIENE UNA TEMPERATURA INFERIOR A 400JC; Y REDUCIR EL RESIDUO OXIDADO PARA FORMAR UN MATERIAL DE MAYOR ACTIVIDAD SUPERFICIAL, LO QUE MEJORA SU SINTERABILIDAD.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US34059382A | 1982-01-19 | 1982-01-19 |
Publications (2)
Publication Number | Publication Date |
---|---|
ES519079A0 ES519079A0 (es) | 1985-08-16 |
ES8507287A1 true ES8507287A1 (es) | 1985-08-16 |
Family
ID=23334074
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES519079A Expired ES8507287A1 (es) | 1982-01-19 | 1983-01-18 | Metodo para tratar residuo de combustible nuclear a base de uo2. |
Country Status (5)
Country | Link |
---|---|
EP (1) | EP0084129B1 (es) |
JP (1) | JPS58124998A (es) |
KR (1) | KR840003215A (es) |
DE (1) | DE3271902D1 (es) |
ES (1) | ES8507287A1 (es) |
Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0150737B1 (en) * | 1984-01-26 | 1989-10-04 | Westinghouse Electric Corporation | Process for treating nuclear fuel scrap |
EP0236298B1 (de) * | 1985-09-09 | 1990-01-17 | Günther Förster | Verfahren und vorrichtung zur verbrennung fester und/oder flüssiger materialien |
FR2599883B1 (fr) * | 1986-06-10 | 1990-08-10 | Franco Belge Fabric Combustibl | Procede de fabrication de pastilles de combustible nucleaire a base d'oxyde d'uranium |
KR100794071B1 (ko) | 2006-12-05 | 2008-01-10 | 한국원자력연구원 | 핵연료 소결체의 제조 방법 |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3140151A (en) * | 1959-11-12 | 1964-07-07 | James R Foltz | Method of reprocessing uo2 reactor fuel |
FR1315822A (fr) * | 1961-12-11 | 1963-01-25 | Commissariat Energie Atomique | Procédé de traitement d'une poudre de bioxyde d'uranium en vue de-la rendre particulièrement apte au frittage et produit obtenu suivant ce procédé |
US3343926A (en) * | 1966-02-08 | 1967-09-26 | Irving E Knudsen | Oxidation-reduction procedure for particle-size reduction of uo2 |
US3578419A (en) * | 1967-12-14 | 1971-05-11 | Gen Electric | Scrap nuclear fuel material recovery process |
FR2001113A1 (fr) * | 1968-02-01 | 1969-09-26 | Nukem Gmbh | Procede pour le traitement a sec de grenaille de combustible nucleaire uo2 ceramique,ainsi que les produits obtenus |
DE2004967A1 (de) * | 1969-03-14 | 1970-09-24 | The Babcock & Wilcox Company, New York, N.Y. (V.St.A.) | Verfahren zur Rückgewinnung von Bestandteilen aus Kernbrennstoff-Schrott |
-
1982
- 1982-12-15 EP EP82111635A patent/EP0084129B1/en not_active Expired
- 1982-12-15 DE DE8282111635T patent/DE3271902D1/de not_active Expired
-
1983
- 1983-01-18 ES ES519079A patent/ES8507287A1/es not_active Expired
- 1983-01-19 JP JP58005968A patent/JPS58124998A/ja active Granted
- 1983-01-19 KR KR1019830000184A patent/KR840003215A/ko not_active Application Discontinuation
Also Published As
Publication number | Publication date |
---|---|
DE3271902D1 (en) | 1986-08-07 |
EP0084129B1 (en) | 1986-07-02 |
EP0084129A2 (en) | 1983-07-27 |
JPH0322600B2 (es) | 1991-03-27 |
JPS58124998A (ja) | 1983-07-25 |
EP0084129A3 (en) | 1983-12-14 |
ES519079A0 (es) | 1985-08-16 |
KR840003215A (ko) | 1984-08-20 |
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