ES8700485A1 - Procedimiento para tratar residuos de combustible nuclear - Google Patents

Procedimiento para tratar residuos de combustible nuclear

Info

Publication number
ES8700485A1
ES8700485A1 ES539724A ES539724A ES8700485A1 ES 8700485 A1 ES8700485 A1 ES 8700485A1 ES 539724 A ES539724 A ES 539724A ES 539724 A ES539724 A ES 539724A ES 8700485 A1 ES8700485 A1 ES 8700485A1
Authority
ES
Spain
Prior art keywords
scrap
nuclear fuel
fluoride
moisture content
steam
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
ES539724A
Other languages
English (en)
Other versions
ES539724A0 (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 ES8700485A1 publication Critical patent/ES8700485A1/es
Publication of ES539724A0 publication Critical patent/ES539724A0/es
Expired legal-status Critical Current

Links

Classifications

    • 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
    • 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)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Processing Of Solid Wastes (AREA)
  • Treating Waste Gases (AREA)

Abstract

METODO DE TRATAMIENTO DE RESIDUOS DE COMBUSTIBLE NUCLEAR EN UN REACTOR DE LECHO DE POLVO PULSADO. COMPRENDE LA FLUIDIZACION DE LOS RESIDUOS EN DICHO REACTOR POR CONTACTO DE LOS MISMOS CON UNA CORRIENTE DE FLUIDO EN EL INTERIOR DEL LECHO FLUIDIZADO, CONSTITUIDO DICHO FLUIDO POR GAS NITROGENO QUE CONTIENE VAPOR Y EVENTUALMENTE POR HIDROGENO, A UNA TEMPERATURA COMPRENDIDA ENTRE 500JC Y 650JC, DURANTE 2-3 HORAS, CUANDO LOS RESIDUOS CONTIENEN UNA ELEVADA PROPORCION DE FLUOR; O CONSTITUIDO POR GAS NITROGENO A UNA TEMPERATURA COMPRENDIDA ENTRE 150JC Y 300JC, DURANTE 1-2 HORAS, CUANDO LOS RESIDUOS TIENEN CONCENTRACIONES ALTAS DE HUMEDAD.
ES539724A 1984-01-26 1985-01-21 Procedimiento para tratar residuos de combustible nuclear Expired ES8700485A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US57430584A 1984-01-26 1984-01-26

Publications (2)

Publication Number Publication Date
ES8700485A1 true ES8700485A1 (es) 1986-10-16
ES539724A0 ES539724A0 (es) 1986-10-16

Family

ID=24295546

Family Applications (1)

Application Number Title Priority Date Filing Date
ES539724A Expired ES8700485A1 (es) 1984-01-26 1985-01-21 Procedimiento para tratar residuos de combustible nuclear

Country Status (5)

Country Link
EP (1) EP0150737B1 (es)
JP (1) JPH06103351B2 (es)
KR (1) KR910008356B1 (es)
DE (1) DE3573487D1 (es)
ES (1) ES8700485A1 (es)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB9411096D0 (en) * 1994-06-03 1994-07-27 British Nuclear Fuels Plc Uranium oxide production
FR2786116B1 (fr) * 1998-11-19 2001-01-12 Franco Belge Combustibles Procede et installation de traitement d'une poudre combustible nucleaire

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4053559A (en) * 1976-06-14 1977-10-11 Westinghouse Electric Corporation Production of uranium dioxide
DE2855166C2 (de) * 1978-12-20 1982-05-27 Kraftwerk Union AG, 4330 Mülheim Verfahren zur Herstellung von oxidischen Kernbrennstoffkörpern
EP0084129B1 (en) * 1982-01-19 1986-07-02 Westinghouse Electric Corporation Method for treating nuclear fuel scrap

Also Published As

Publication number Publication date
JPS60170797A (ja) 1985-09-04
DE3573487D1 (en) 1989-11-09
JPH06103351B2 (ja) 1994-12-14
KR850005707A (ko) 1985-08-28
EP0150737B1 (en) 1989-10-04
EP0150737A2 (en) 1985-08-07
ES539724A0 (es) 1986-10-16
KR910008356B1 (ko) 1991-10-12
EP0150737A3 (en) 1986-03-12

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