ES8103433A1 - Procedimiento y dispositivo para la fabricacion de cuerpos de combustible nuclear oxidicos - Google Patents

Procedimiento y dispositivo para la fabricacion de cuerpos de combustible nuclear oxidicos

Info

Publication number
ES8103433A1
ES8103433A1 ES486920A ES486920A ES8103433A1 ES 8103433 A1 ES8103433 A1 ES 8103433A1 ES 486920 A ES486920 A ES 486920A ES 486920 A ES486920 A ES 486920A ES 8103433 A1 ES8103433 A1 ES 8103433A1
Authority
ES
Spain
Prior art keywords
nuclear fuel
manufacturing
fuel elements
stage
blanks
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
ES486920A
Other languages
English (en)
Other versions
ES486920A0 (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 ES486920A0 publication Critical patent/ES486920A0/es
Publication of ES8103433A1 publication Critical patent/ES8103433A1/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)
  • Powder Metallurgy (AREA)
  • Compositions Of Oxide Ceramics (AREA)

Abstract

PROCEDIMIENTO PARA LA FABRICACION DE CUERPOS DE COMBUSTIBLE NUCLEAR OXIDICOS CON UNA RELACION DE OXIGENO A METAL DE 2,0 +- 0,02 A TEMPERATURA DE SINTERIZACION ENTRE 1.000 Y 1.400 GC. EL HORNO SE DESIGNA EN LA FIGURA POR (2). EL PRODUCTO DE SINTERIZACION SE INTRODUCE EN LA ZONA DE SINTERIZACION A UNA TEMPERATURA DE 1.100 GC (S), CIRCULANDO EN EL MISMO SENTIDO GAS (5) CO2, QUE SE EVACUA POR LA EXCLUSA (7), LA CUAL VA BAÑADA DE NITROGENO. LUEGO PASA EL PRODUCTO DE SINTERIZACION A LA ZONA DE REDUCCION (R), QUE SE ENCUENTRA TAMBIEN A 1.100GC., PARA PASAR A CONTINUACION A LA ZONA DE ENFRIAMIENTO (A). EL GAS REDUCTOR (6) ES UNA MEZCLA DE HIDROGENO Y NITROGENO QUE FLUYE EN SENTIDO CONTRARIO AL PRODUCTO A SINTERIZAR, SIENDO EVACUADO POR LA EXCLUSA (7). POR EL EMPLEO DE DIOXIDO DE CARBONO TECNICAMENTE PURO, SE AJUSTA LA SOBREESTEQUIOMETRIA NECESARIA PARA EL PROCESO DE SINTERIZACION, DE TAL FORMA QUE PARA TEMPERATURAS DE 1.000º. SE NECESITAN PERMANENCIAS DE 30 MINUTOS, MIENTRAS QUE PARA 1.400GC. SE REQUIEREN 5 MINUTOS.
ES486920A 1978-12-20 1979-12-14 Procedimiento y dispositivo para la fabricacion de cuerpos de combustible nuclear oxidicos Expired ES8103433A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2855166A DE2855166C2 (de) 1978-12-20 1978-12-20 Verfahren zur Herstellung von oxidischen Kernbrennstoffkörpern

Publications (2)

Publication Number Publication Date
ES486920A0 ES486920A0 (es) 1981-02-16
ES8103433A1 true ES8103433A1 (es) 1981-02-16

Family

ID=6057816

Family Applications (1)

Application Number Title Priority Date Filing Date
ES486920A Expired ES8103433A1 (es) 1978-12-20 1979-12-14 Procedimiento y dispositivo para la fabricacion de cuerpos de combustible nuclear oxidicos

Country Status (7)

Country Link
US (1) US4348339A (es)
EP (1) EP0012915B1 (es)
JP (1) JPS5587089A (es)
BR (1) BR7908328A (es)
CA (1) CA1122398A (es)
DE (2) DE2855166C2 (es)
ES (1) ES8103433A1 (es)

Families Citing this family (21)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2939415C2 (de) * 1979-09-28 1981-11-26 Kraftwerk Union AG, 4330 Mülheim Verfahren zur Herstellung von hochdichten oxidischen Kernbrennstoffkörpern
US4389355A (en) * 1981-07-23 1983-06-21 The Babcock & Wilcox Company Sintering UO2 and oxidation of UO2 with microwave radiation
DE3142447C1 (de) * 1981-10-26 1983-04-14 Kraftwerk Union AG, 4330 Mülheim Verfahren zum Herstellen von oxidischen Kernbrennstoffsinterkoerpern
DE3310789A1 (de) * 1983-03-24 1984-09-27 Kraftwerk Union AG, 4330 Mülheim Verfahren und tunnelofen zum sintern von gruenlingen
DE3573487D1 (en) * 1984-01-26 1989-11-09 Westinghouse Electric Corp Process for treating nuclear fuel scrap
DE3519825A1 (de) * 1985-06-03 1986-12-04 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
JPS62225993A (ja) * 1986-03-27 1987-10-03 日本ニユクリア・フユエル株式会社 セラミツク核燃料焼結体の製造法
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
GB8702371D0 (en) * 1987-02-03 1987-03-11 British Nuclear Fuels Plc Pellet fabrication
US4869866A (en) * 1987-11-20 1989-09-26 General Electric Company Nuclear fuel
US4869868A (en) * 1987-11-23 1989-09-26 General Electric Company Nuclear fuel
US5641435A (en) * 1995-09-22 1997-06-24 General Electric Company Control of residual gas content of nuclear fuel
JPH09127290A (ja) * 1995-11-06 1997-05-16 Mitsubishi Nuclear Fuel Co Ltd 核燃料ペレットの焼結方法
DE19633312A1 (de) * 1996-08-19 1998-02-26 Siemens Ag Verfahren zum Sintern von Pellets aus Nuklearbrennstoff
FR2827072B1 (fr) * 2001-07-04 2005-12-02 Commissariat Energie Atomique Procede de fabrication d'un materiau combustible nucleaire composite constitue d'amas d'(u,pu)o2 disperses dans une matrice de uo2
JP3593515B2 (ja) * 2001-10-02 2004-11-24 原子燃料工業株式会社 核燃料焼結体の製造方法
KR101535173B1 (ko) * 2013-12-27 2015-07-10 한국원자력연구원 산화물 핵연료의 제조방법 및 이에 따라 제조되는 산화물 핵연료
DE102014114093B4 (de) * 2014-09-29 2017-03-23 Danfoss Silicon Power Gmbh Verfahren zum Niedertemperatur-Drucksintern
DE102014114096A1 (de) 2014-09-29 2016-03-31 Danfoss Silicon Power Gmbh Sinterwerkzeug für den Unterstempel einer Sintervorrichtung
DE102014114097B4 (de) 2014-09-29 2017-06-01 Danfoss Silicon Power Gmbh Sinterwerkzeug und Verfahren zum Sintern einer elektronischen Baugruppe

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE579387A (es) * 1958-06-06
US3094377A (en) * 1960-03-29 1963-06-18 Sylvania Electric Prod Method for producing high density uranium oxide
US3375306A (en) * 1960-04-29 1968-03-26 Atomic Energy Authority Uk Method of producing dense,sintered bodies of uo2 or uo2-puo2 mixtures
US3258317A (en) * 1963-04-25 1966-06-28 Ca Atomic Energy Ltd Preparation of dense uranium oxide
US3179392A (en) * 1963-12-03 1965-04-20 Btu Eng Corp Heat and gas barrier for muffle furnaces
FR1430350A (fr) * 1965-01-21 1966-03-04 Commissariat Energie Atomique Procédé de fabrication d'éléments combustibles pour réacteur nucléaire et éléments combustibles obtenus
GB1208433A (en) * 1967-04-20 1970-10-14 Atomic Energy Authority Uk Manufacture of ceramic artefacts having pores
US3578419A (en) * 1967-12-14 1971-05-11 Gen Electric Scrap nuclear fuel material recovery process
GB1274112A (en) * 1969-01-08 1972-05-10 Snam Progetti Improvements in or relating to the production of refractory material
US3930787A (en) * 1970-08-10 1976-01-06 General Electric Company Sintering furnace with hydrogen carbon dioxide atmosphere
GB1332928A (en) * 1970-11-20 1973-10-10 Belousov A A Controlled-atmosphere furnace with gas seal
DE2115694C3 (de) * 1971-03-31 1973-12-06 Snam Progetti S.P.A., Mailand (Italien) Verfahren zum Herstellen von Uranoxyd kugelchen oder gemischten Uranoxyd Plutomumoxydkugelchen mit steuerbarer Porosität
US3761546A (en) * 1972-05-22 1973-09-25 Atomic Energy Commission Method of making uranium dioxide bodies
US4052330A (en) * 1975-03-20 1977-10-04 Gen Electric Sintering uranium oxide using a preheating step

Also Published As

Publication number Publication date
ES486920A0 (es) 1981-02-16
JPS6119952B2 (es) 1986-05-20
CA1122398A (en) 1982-04-27
US4348339A (en) 1982-09-07
DE2855166A1 (de) 1980-06-26
EP0012915A1 (de) 1980-07-09
JPS5587089A (en) 1980-07-01
DE2966996D1 (en) 1984-06-20
DE2855166C2 (de) 1982-05-27
EP0012915B1 (de) 1984-05-16
BR7908328A (pt) 1980-09-16

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19970401