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ES8402968A1 - Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear oxidico. - Google Patents

Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear oxidico.

Info

Publication number
ES8402968A1
ES8402968A1 ES516804A ES516804A ES8402968A1 ES 8402968 A1 ES8402968 A1 ES 8402968A1 ES 516804 A ES516804 A ES 516804A ES 516804 A ES516804 A ES 516804A ES 8402968 A1 ES8402968 A1 ES 8402968A1
Authority
ES
Spain
Prior art keywords
gas atmosphere
nuclear fuel
fuel bodies
manufacturing sintered
oxidizing action
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
ES516804A
Other languages
English (en)
Other versions
ES516804A0 (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.)
Reaktor Brennelement Union GmbH
Kraftwerk Union AG
Original Assignee
Reaktor Brennelement Union GmbH
Kraftwerk Union AG
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 Reaktor Brennelement Union GmbH, Kraftwerk Union AG filed Critical Reaktor Brennelement Union GmbH
Publication of ES8402968A1 publication Critical patent/ES8402968A1/es
Publication of ES516804A0 publication Critical patent/ES516804A0/es
Granted 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
    • 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)
  • Compositions Of Oxide Ceramics (AREA)
  • Powder Metallurgy (AREA)
  • Inert Electrodes (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

PROCEDIMIENTO PARA LA OBTENCION DE CUERPOS SINTERIZADOS DE COMBUSTIBLE NUCLEAR OXIDICO.CONSISTE EN EL TRATAMIENTO TERMICO DE AGLOMERADOS PRENSADOS DE OBTENIDOS DE POLVOS DE PARTIDA DE UO2 O DE UNA MEZCLA DE POLVOS DEPARTIDA DE UO2 Y PUO2 A UNA TEMPERATURA ENTRE 1.000 Y 1.400JC, EN ATMOSFERA DE GAS OXIDANTE, Y A CONTINUACION EN ATMOSFERA DE GAS CON EFECTO REDUCTOR. EL POTENCIAL DE OXIGENO DE LA ATMOSFERA DE GAS DE EFECTO OXIDANTE SE MANTIENE EN UN MARGEN EN EL QUE LOS AGLOMERADOS PRENSADOS DURANTE EL CALENTAMIENTO A LA TEMPERATURA DE TRATAMIENTO GENERAN UNA FASE CRISTALINADE U4O9 O DE (U, PU)4O9. EL GAS OXIDANTE UTILIZADO ES UNA MEZCLA DE CO2 Y AIRE EN LA PROPORCION 105:1 HASTA 102:1. LOS POLVOS AGLOMERADOS PRENSADOS CON POLVOS DE UO2 PRESENTAN UNA SUPERFICIE ESPECIFICA DE 4M2/G A 7M2/G Y UN TAMAÑO DE CRISTALITO INFERIOR A 0,7 BMBM.
ES516804A 1981-10-26 1982-10-25 Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear oxidico. Granted ES516804A0 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE3142447A DE3142447C1 (de) 1981-10-26 1981-10-26 Verfahren zum Herstellen von oxidischen Kernbrennstoffsinterkoerpern

Publications (2)

Publication Number Publication Date
ES8402968A1 true ES8402968A1 (es) 1984-02-16
ES516804A0 ES516804A0 (es) 1984-02-16

Family

ID=6144864

Family Applications (1)

Application Number Title Priority Date Filing Date
ES516804A Granted ES516804A0 (es) 1981-10-26 1982-10-25 Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear oxidico.

Country Status (7)

Country Link
US (1) US4578229A (es)
EP (1) EP0078428B1 (es)
JP (1) JPS5882189A (es)
BR (1) BR8206197A (es)
CA (1) CA1182994A (es)
DE (1) DE3142447C1 (es)
ES (1) ES516804A0 (es)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3519825A1 (de) * 1985-06-03 1986-12-04 Kraftwerk Union AG, 4330 Mülheim Verfahren zum herstellen von oxidischen kernbrennstoffsinterkoerpern
US4871479A (en) * 1986-03-25 1989-10-03 Comurhex Societe Pour La Conversion De L'uranium En Metal Et Hexafluorure Process for producing sintered mixed oxides which are soluble in nitric acid from solutions of nitrates
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
GB8724514D0 (en) * 1987-10-20 1987-11-25 British Nuclear Fuels Plc Production of ceramic nuclear fuel pellets
JP2701043B2 (ja) * 1988-05-31 1998-01-21 ニュークリア・デベロップメント株式会社 ２重微細構造を有する酸化物核燃料体の製造方法
FR2655467B1 (fr) * 1989-12-05 1994-02-25 Pechiney Uranium Procede d'obtention de pastilles combustibles d'uo2 a partir d'u metal, sans production d'effluent.
DE19812320C1 (de) * 1998-03-20 1999-11-04 Siemens Ag Verfahren zur Herstellung von Kernbrennstoff-Sinterkörpern und entsprechende Sinterkörper
RU2182378C2 (ru) * 2000-04-11 2002-05-10 Государственный научный центр Российской Федерации Всероссийский научно-исследовательский институт неорганических материалов им. академика А.А. Бочвара Способ получения спеченного оксида урана
KR100964953B1 (ko) * 2008-10-15 2010-06-21 한국원자력연구원 ＵＯ₂격자 내 Ｃｒ 고용도를 조절하여 큰 결정립 핵연료 소결체를 제조하는 방법
KR101535173B1 (ko) * 2013-12-27 2015-07-10 한국원자력연구원 산화물 핵연료의 제조방법 및 이에 따라 제조되는 산화물 핵연료

Family Cites Families (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB881883A (en) * 1959-06-22 1961-11-08 Atomic Energy Authority Uk Improvements in or relating to production of uranium oxide bodies
NL273051A (es) * 1960-12-30
BE720704A (es) * 1967-12-21 1969-02-17
DE1939610A1 (de) * 1968-08-05 1970-02-19 Gen Electric Verfahren zur Herstellung eines Kernbrennstoffes aus gesintertem Urandioxyd
US3927154A (en) * 1968-08-05 1975-12-16 Gen Electric Process for preparing sintered uranium dioxide nuclear fuel
US4052330A (en) * 1975-03-20 1977-10-04 Gen Electric Sintering uranium oxide using a preheating step
US4053559A (en) * 1976-06-14 1977-10-11 Westinghouse Electric Corporation Production of uranium dioxide
IT1096285B (it) * 1978-05-05 1985-08-26 Agipnucleare S P A Comitato Na Metodo di fabbricazione di pastiglie di materiale ceramico
DE2855166C2 (de) * 1978-12-20 1982-05-27 Kraftwerk Union AG, 4330 Mülheim Verfahren zur Herstellung von oxidischen Kernbrennstoffkörpern

Also Published As

Publication number Publication date
EP0078428A2 (de) 1983-05-11
EP0078428A3 (en) 1983-09-21
BR8206197A (pt) 1983-09-20
US4578229A (en) 1986-03-25
JPH0471193B2 (es) 1992-11-13
JPS5882189A (ja) 1983-05-17
CA1182994A (en) 1985-02-26
ES516804A0 (es) 1984-02-16
EP0078428B1 (de) 1985-04-10
DE3142447C1 (de) 1983-04-14

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19970519