ES8402969A1 - Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear a base de oxidos. - Google Patents

Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear a base de oxidos.

Info

Publication number
ES8402969A1
ES8402969A1 ES517203A ES517203A ES8402969A1 ES 8402969 A1 ES8402969 A1 ES 8402969A1 ES 517203 A ES517203 A ES 517203A ES 517203 A ES517203 A ES 517203A ES 8402969 A1 ES8402969 A1 ES 8402969A1
Authority
ES
Spain
Prior art keywords
manufacture
nuclear fuel
range
starting powder
sintered bodies
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
ES517203A
Other languages
English (en)
Other versions
ES517203A0 (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 ES517203A0 publication Critical patent/ES517203A0/es
Publication of ES8402969A1 publication Critical patent/ES8402969A1/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
    • 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)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Inert Electrodes (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PROCEDIMIENTO PARA LA OBTENCION DE CUERPOS SINTERIZADOS DE COMBUSTIBLE NUCLEAR A BASE DE OXIDOS.CONSISTE EN COMPACTAR POLVO DE PARTIDA A BASE DE UO2 Y DE PU O2, QUE CONTIENEN HASTA UN 10 EN PESO DE OXIDO DE TIERRAS RARAS, GD2O3, COMO ADITIVO, EN FORMA DE BRIQUETAS Y A CONTINUACION SE REALIZA UNA DENSIFICACION DE ESTAS BRIQUETAS MEDIANTE UN TRATAMIENTO TERMICO EN UNA ATMOSFERA SINTERIZADORA QUE ACTUA DE FORMA REDUCTORA; EN EL QUE SE EMPLEA PARA EL COMPACTADO POLVO DE PARTIDA A BASE DE UO2 CON UNA SUPERFICIE ESPECIFICA COMPRENDIDA ENTRE 2 Y 4,5 M2/G Y/O DIAMETROMEDIO DE LA CRISTALITA COMPRENDIDO ENTRE 80 Y 250 BMBM Y SE EFECTUA EL TRATAMIENTO TERMICO SINTERIZADOR EN ATMOSFERA REDUCTORA A TEMPERATURAS COMPRENDIDAS ENTRE 1.500 Y 1.750JC, SIENDO LA VELOCIDAD DE CALENTAMIENTO ENTRE 1JC/MINUTO Y A 10JC/MINUTO HASTA LA TEMPERATURA DEL TRATAMIENTO TERMICO QUE SE MANTIENE DURANTE UN TIEMPO COMPRENDIDO ENTRE 1 HORA Y 10 HORAS.
ES517203A 1981-11-10 1982-11-08 Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear a base de oxidos. Expired ES8402969A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE3144684A DE3144684C1 (de) 1981-11-10 1981-11-10 Verfahren zum Herstellen von oxidischen Kernbrennstoffsinterkoerpern

Publications (2)

Publication Number Publication Date
ES517203A0 ES517203A0 (es) 1984-02-16
ES8402969A1 true ES8402969A1 (es) 1984-02-16

Family

ID=6146069

Family Applications (1)

Application Number Title Priority Date Filing Date
ES517203A Expired ES8402969A1 (es) 1981-11-10 1982-11-08 Procedimiento para la obtencion de cuerpos sinterizados de combustible nuclear a base de oxidos.

Country Status (7)

Country Link
US (1) US4512939A (es)
EP (1) EP0079031B1 (es)
JP (1) JPS5892987A (es)
BR (1) BR8206497A (es)
CA (1) CA1182995A (es)
DE (1) DE3144684C1 (es)
ES (1) ES8402969A1 (es)

Families Citing this family (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3425581A1 (de) * 1983-10-06 1985-04-25 Kraftwerk Union AG, 4330 Mülheim Verfahren zum herstellen von oxidischen kernbrennstoffsinterkoerpern
SE439854B (sv) * 1983-12-20 1985-07-01 Asea Atom Ab Sett att framstella sintrade kernbrenslekroppar
DE3406084A1 (de) * 1984-02-20 1985-08-22 Kraftwerk Union AG, 4330 Mülheim Verfahren zum herstellen von oxidischen kernbrennstoffsinterkoerpern
SE452153B (sv) * 1985-09-18 1987-11-16 Asea Atom Ab Sett att tillverka sintrade kernbrenslekroppar
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
US5180527A (en) * 1990-04-03 1993-01-19 Nippon Nuclear Fuel Development Co., Ltd. Nuclear fuel pellets
US5255299A (en) * 1990-04-03 1993-10-19 Nippon Nuclear Fuel Development Co., Ltd. Method of manufacturing nuclear fuel pellets
GB9511396D0 (en) * 1995-06-06 1995-08-02 British Nuclear Fuels Plc Chemical complexes
GB9515966D0 (en) * 1995-08-03 1995-10-04 British Nuclear Fuels Plc Nuclear fuel pellets
FR2744557B1 (fr) * 1996-02-07 1998-02-27 Commissariat Energie Atomique Materiau combustible nucleaire composite et procede de fabrication du materiau
FR2894954B1 (fr) * 2005-12-19 2008-02-15 Commissariat Energie Atomique Procede de fabrication d'une matiere particulaire et matiere particulaire susceptible d'etre obtenue par ledit procede.
FR2895137B1 (fr) * 2005-12-19 2008-02-15 Commissariat Energie Atomique Procede de fabrication d'un materiau dense pour combustible nucleaire et produit susceptible d'etre obtenu par ce procede.
KR101677175B1 (ko) * 2015-08-07 2016-11-21 서울시립대학교 산학협력단 기지상보다 수축율이 큰 코팅층을 갖는 삼층구조 등방성 핵연료 입자를 포함하는 완전 세라믹 캡슐형 핵연료 조성물, 소재 및 그 제조방법
WO2017171937A1 (en) * 2016-03-29 2017-10-05 Ultra Safe Nuclear Corporation Fully ceramic microencapsulated fuel fabricated with burnable poison as sintering aid

Family Cites Families (19)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3168601A (en) * 1960-10-28 1965-02-02 Gen Electric Process for the production of plutonium oxide-containing nuclear fuel compacts
US3862908A (en) * 1962-05-03 1975-01-28 Grace W R & Co Microspheres of urania and other materials
GB1116663A (en) * 1965-01-22 1968-06-12 Atomic Energy Authority Uk Sintered uranium dioxide
US3374178A (en) * 1965-05-03 1968-03-19 Ca Atomic Energy Ltd Doped hypostoichiometric dioxide nuclear fuel composition and method of preparation
US3361857A (en) * 1965-12-03 1968-01-02 Westinghouse Electric Corp Method of preparing a fuel element of fissionable oxide and burnable poison
BE682181A (es) * 1966-06-07 1966-11-14
GB1274112A (en) * 1969-01-08 1972-05-10 Snam Progetti Improvements in or relating to the production of refractory material
CH504914A (fr) * 1969-02-25 1971-03-31 Belgonucleaire Sa Procédé de fabrication de pastilles de combustible nucléaire
DE1911564A1 (de) * 1969-03-07 1970-09-24 Nukem Gmbh Brennelement mit oxidischem Brennstoff fuer Kernreaktoren
FR2041615A5 (es) * 1969-05-02 1971-01-29 Commissariat Energie Atomique
FR2061557A1 (es) * 1969-06-27 1971-06-25 Commissariat Energie Atomique
SE366015B (es) * 1970-08-10 1974-04-08 Gen Electric
CA1023935A (en) * 1975-02-28 1978-01-10 Her Majesty In Right Of Canada As Represented By Atomic Energy Of Canada Limited Preparation of mixed oxide nuclear fuel
DE2601684C3 (de) * 1976-01-17 1978-12-21 Hobeg Hochtemperaturreaktor-Brennelement Gmbh, 6450 Hanau Verfahren zur Herstellung von Brenn- und Brutstoff-Partikeln
US4094738A (en) * 1976-05-19 1978-06-13 Westinghouse Electric Corp. Nuclear fuel pellet design to minimize dimensional changes
DE2833054C2 (de) * 1978-07-27 1982-07-01 Alkem Gmbh, 6450 Hanau Verfahren zur Herstellung von PuO↓2↓/UO↓2↓-Kernbrennstoffen
DE2853599C3 (de) * 1978-12-12 1981-09-03 Reaktor-Brennelement Union Gmbh, 6450 Hanau Verfahren zur Herstellung von Gadolinium enthaltenden Kernbrennstoffen
DE2939415C2 (de) * 1979-09-28 1981-11-26 Kraftwerk Union AG, 4330 Mülheim Verfahren zur Herstellung von hochdichten oxidischen Kernbrennstoffkörpern
US4409157A (en) * 1981-01-21 1983-10-11 Haas Paul A Method for improved decomposition of metal nitrate solutions

Also Published As

Publication number Publication date
CA1182995A (en) 1985-02-26
BR8206497A (pt) 1983-09-27
EP0079031A1 (de) 1983-05-18
JPS5892987A (ja) 1983-06-02
US4512939A (en) 1985-04-23
ES517203A0 (es) 1984-02-16
DE3144684C1 (de) 1983-04-14
JPH0338557B2 (es) 1991-06-11
EP0079031B1 (de) 1985-05-08

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