ES471633A1 - Procedimiento y su correspondiente aparato para recuperar enforma de solucion compuestos de combustible nuclear enrique-cidos procedentes de materiales residuales - Google Patents

Procedimiento y su correspondiente aparato para recuperar enforma de solucion compuestos de combustible nuclear enrique-cidos procedentes de materiales residuales

Info

Publication number
ES471633A1
ES471633A1 ES471633A ES471633A ES471633A1 ES 471633 A1 ES471633 A1 ES 471633A1 ES 471633 A ES471633 A ES 471633A ES 471633 A ES471633 A ES 471633A ES 471633 A1 ES471633 A1 ES 471633A1
Authority
ES
Spain
Prior art keywords
acid solution
nuclear fuel
acid
scrap materials
recycled
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
Application number
ES471633A
Other languages
English (en)
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Publication of ES471633A1 publication Critical patent/ES471633A1/es
Expired legal-status Critical Current

Links

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
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • 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
    • 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
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Processing Of Solid Wastes (AREA)
  • Extraction Or Liquid Replacement (AREA)

Abstract

Procedimiento y su correspondiente aparato para recuperar en forma de solución compuestos de combustible nuclear enriquecidos procedentes de materiales residuales, estando dicho procedimiento caracterizado porque incluye las operaciones que consisten en: (a) calcinar el material residual, que es fácilmente combustible para obtener un material oxidado; (b) dividir finamente el material oxidado para formar un material en partículas de tamaño inferior a 250 micrones aproximadamente; (c) poner en contacto el material en forma de partículas con un ácido que contiene una cierta cantidad de ácido reciclado en la etapa (g) en una zona de extracción de forma plana agitada mecánicamente y de configuración segura desde el punto de vista nuclear para disolver dichos compuestos y obtener una solución ácida de dichos compuestos; (d) triturar el material no combustible tal como los medios de filtración de modo que se presenten bajo la forma de un material constituido por partículas; (e) poner en contactoel material no combustible triturado con la solución ácida de (c); (f) separar de la solución ácida los sólidos insolubles no en suspensión en una zona filtración; (g) separar los sólidos en suspensión de la solución de ácido en una zona de clarificación; (h) reciclar por lo menos una parte de la solución ácida de (g) procedente de la zona de clarificación hacia la zona de extracción; e (i) recoger el resto de la solución ácida para su tratamiento ulterior.
ES471633A 1977-09-08 1978-07-11 Procedimiento y su correspondiente aparato para recuperar enforma de solucion compuestos de combustible nuclear enrique-cidos procedentes de materiales residuales Expired ES471633A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/831,689 US4177241A (en) 1977-09-08 1977-09-08 Apparatus and process for recovering nuclear fuel from scrap material

Publications (1)

Publication Number Publication Date
ES471633A1 true ES471633A1 (es) 1979-10-01

Family

ID=25259627

Family Applications (1)

Application Number Title Priority Date Filing Date
ES471633A Expired ES471633A1 (es) 1977-09-08 1978-07-11 Procedimiento y su correspondiente aparato para recuperar enforma de solucion compuestos de combustible nuclear enrique-cidos procedentes de materiales residuales

Country Status (7)

Country Link
US (1) US4177241A (es)
JP (1) JPS5452297A (es)
BE (1) BE888345Q (es)
DE (1) DE2839010A1 (es)
ES (1) ES471633A1 (es)
IT (1) IT1098752B (es)
SE (1) SE7809443L (es)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2050039B (en) * 1979-04-30 1983-01-19 Atomic Energy Authority Uk Dissolving plutanium containing nuclear fuels
JPS60249098A (ja) * 1984-05-25 1985-12-09 株式会社東芝 放射能汚染金属の除染装置
JPS60249099A (ja) * 1984-05-25 1985-12-09 株式会社東芝 放射能汚染金属の除染装置
JPS60249097A (ja) * 1984-05-25 1985-12-09 株式会社東芝 放射能で汚染された金属の除染装置
US4656015A (en) * 1984-09-17 1987-04-07 General Electric Company Continuous process for the production of powdered uranium dioxide from uranyl nitrate
US5077020A (en) * 1989-12-20 1991-12-31 Westinghouse Electric Corp. Metal recovery process using waterglass
GB2256379A (en) * 1991-06-07 1992-12-09 Joachim Wolf Method/apparatus for disposing of filter cartridges.
US5514306A (en) * 1993-02-01 1996-05-07 General Electric Company Process to reclaim UO2 scrap powder
US5368829A (en) * 1993-09-09 1994-11-29 Westinghouse Electric Corporation Continuous ash extraction process
US7527772B2 (en) * 2004-07-01 2009-05-05 Areva Np Inc. Ultrasonic counter-current screw extractor for uranium recovery and process therefore

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3488162A (en) * 1967-10-20 1970-01-06 Adam E Sierzputowski Oxidative treatment of uranium ore prior to acid leach
US3578419A (en) * 1967-12-14 1971-05-11 Gen Electric Scrap nuclear fuel material recovery process
DE1958464A1 (de) * 1969-11-21 1971-06-03 Alkem Gmbh Verfahren zur nasschemischen Verbrennung von organischem Material

Also Published As

Publication number Publication date
IT1098752B (it) 1985-09-18
DE2839010A1 (de) 1979-03-22
BE888345Q (fr) 1981-10-09
IT7827128A0 (it) 1978-08-30
US4177241A (en) 1979-12-04
SE7809443L (sv) 1979-03-09
JPS5452297A (en) 1979-04-24

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 20001204