ES519079A0 - 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
ES519079A0
ES519079A0 ES519079A ES519079A ES519079A0 ES 519079 A0 ES519079 A0 ES 519079A0 ES 519079 A ES519079 A ES 519079A ES 519079 A ES519079 A ES 519079A ES 519079 A0 ES519079 A0 ES 519079A0
Authority
ES
Spain
Prior art keywords
nuclear fuel
fuel waste
waste based
treating nuclear
treating
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.)
Granted
Application number
ES519079A
Other languages
English (en)
Other versions
ES8507287A1 (es
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Westinghouse Electric Corp
Original Assignee
Westinghouse Electric Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of ES519079A0 publication Critical patent/ES519079A0/es
Publication of ES8507287A1 publication Critical patent/ES8507287A1/es
Expired legal-status Critical Current

Links

Classifications

    • BPERFORMING OPERATIONS; TRANSPORTING
    • B01PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01JCHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
    • B01J8/00Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes
    • B01J8/18Chemical or physical processes in general, conducted in the presence of fluids and solid particles; Apparatus for such processes with fluidised particles
    • B01J8/24Chemical 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
    • B01J8/40Chemical 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • C01G43/01Oxides; Hydroxides
    • C01G43/025Uranium dioxide
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/623Oxide fuels
    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01PINDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00Physical properties of inorganic compounds
    • C01P2006/80Compositional purity
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N1/00Sampling; Preparing specimens for investigation
    • G01N1/02Devices for withdrawing samples
    • G01N1/22Devices for withdrawing samples in the gaseous state
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Combustion & Propulsion (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Inorganic Chemistry (AREA)
  • Ceramic Engineering (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
  • Processing Of Solid Wastes (AREA)
  • Fluidized-Bed Combustion And Resonant Combustion (AREA)
ES519079A 1982-01-19 1983-01-18 Metodo para tratar residuo de combustible nuclear a base de uo2. Expired ES8507287A1 (es)

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 true ES519079A0 (es) 1985-08-16
ES8507287A1 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)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3573487D1 (en) * 1984-01-26 1989-11-09 Westinghouse Electric Corp 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)

* Cited by examiner, † Cited by third party
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
SE346048B (es) * 1968-02-01 1972-06-19 Nukem Gmbh
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

Also Published As

Publication number Publication date
EP0084129B1 (en) 1986-07-02
ES8507287A1 (es) 1985-08-16
JPS58124998A (ja) 1983-07-25
EP0084129A3 (en) 1983-12-14
EP0084129A2 (en) 1983-07-27
KR840003215A (ko) 1984-08-20
DE3271902D1 (en) 1986-08-07
JPH0322600B2 (es) 1991-03-27

Similar Documents

Publication Publication Date Title
ES506070A0 (es) Estructura de combustible para reactor nuclear.
ES296894Y (es) Separador utilizado en un conjunto de combustible de reactor nuclear
ES549537A0 (es) Un separador de desechos en o para un conjunto de combusti- ble nuclear
ES506090A0 (es) Perfeccionamientos en un conjunto combustible de reactor nu-clear
ES536736A0 (es) Conjunto de combustible para reactor nuclear
ES512535A0 (es) Aparato para agrupar a distancia barras de combustible nuclear.
ES506178A0 (es) Conjunto de combustible para reactor nuclear
ES524026A0 (es) Conjunto de combustible nuclear
ES502182A0 (es) Conjunto de combustible para un reactor nuclear
ES520731A0 (es) Metodo y aparato correspondiente para desmontar, cortar y compactar un esqueleto de conjunto de combustible.
ES509675A0 (es) Procedimiento para la obtencion de un combustible microemulsionado.
ES514143A0 (es) Metodo para preparar pastillas de combustible nuclear.
ES535404A0 (es) Perfeccionamientos en elementos combustibles para reactor nuclear
ES519203A0 (es) Perfeccionamientos en los sistemas combustibles de reactor nuclear.
ES493288A0 (es) Metodo para producir un recipiente para combustible nuclear
ES280860Y (es) Rejilla separadora mejorada para conjuntos de combustible nuclear.
ES522718A0 (es) Aparato para recargar con combustible un reactor nuclear.
ES521252A0 (es) Mejoras introducidas en conjuntos de combustible nuclear.
ES519039A0 (es) Perfeccionamientos en una pieza de extremidad de ensamblaje combustible de reactor nuclear.
ES296419Y (es) Elmento combustible para reactor nuclear.
ES525821A0 (es) Metodo para reconstituir un conjunto de combustible de reactor nuclear
ES516185A0 (es) "una disposicion de combustible para un reactor nuclear.
ES535322A0 (es) Metodo para revestir un cuerpo de combustible nuclear con un veneno consumible
ES296612Y (es) Disposicion de combustible para reactor nuclear.
ES520223A0 (es) Un elemento combustible nuclear.