GB1397014A - Fabrication process for nuclear fuel pellets - Google Patents

Fabrication process for nuclear fuel pellets

Info

Publication number
GB1397014A
GB1397014A GB1727773A GB1727773A GB1397014A GB 1397014 A GB1397014 A GB 1397014A GB 1727773 A GB1727773 A GB 1727773A GB 1727773 A GB1727773 A GB 1727773A GB 1397014 A GB1397014 A GB 1397014A
Authority
GB
United Kingdom
Prior art keywords
pellets
compression moulded
pellet
binder
nuclear fuel
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
GB1727773A
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.)
Australian Atomic Energy Commission
Original Assignee
Australian Atomic Energy Commission
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 Australian Atomic Energy Commission filed Critical Australian Atomic Energy Commission
Publication of GB1397014A publication Critical patent/GB1397014A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B35/00Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
    • C04B35/622Forming processes; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
    • C04B35/626Preparing or treating the powders individually or as batches ; preparing or treating macroscopic reinforcing agents for ceramic products, e.g. fibres; mechanical aspects section B
    • C04B35/63Preparing or treating the powders individually or as batches ; preparing or treating macroscopic reinforcing agents for ceramic products, e.g. fibres; mechanical aspects section B using additives specially adapted for forming the products, e.g.. binder binders
    • C04B35/632Organic additives
    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B35/00Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
    • C04B35/51Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on compounds of actinides
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/623Oxide fuels
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Manufacturing & Machinery (AREA)
  • Structural Engineering (AREA)
  • Materials Engineering (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • Inorganic Chemistry (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)

Abstract

1397014 Moulding nuclear fuel pellets AUSTRALIAN ATOMIC ENERGY COMMISSION 10 April 1973 [13 April 1972] 17277/73 Heading B5A [Also in Division G6] A nuclear fuel pellet is produced by extruding a mixture of powdered fuel and binder which is cut at the extruder die into pellets and, after drying, one or more juxtaposed pellets are compression moulded within a die of larger area, and at a pressure greater than that of extrusion, and the compression moulded pellet is sintered. Reject extruded pellets may be recycled to the extruder. The fuel may comprise natural or enriched UO 2 , or PuO 2 , or UO 2 -PuO 2 . The binder may compise camphor, when the sintering is effected in hydrogen or, with a less easily removable binder, debonding may be effected prior to sintering. The extrusion and compression moulded pellets may be of cylindrical solid, or tubular section, and the compression moulded pellet may comprise regions of different fissile content, as in the Fig. 4c embodiment wherein a compression moulded pellet is moulded from extruded pellets 18, 17 of solid and tubular section, between opposed plungers 19, 21.
GB1727773A 1972-04-13 1973-04-10 Fabrication process for nuclear fuel pellets Expired GB1397014A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
AUPA859372 1972-04-13

Publications (1)

Publication Number Publication Date
GB1397014A true GB1397014A (en) 1975-06-11

Family

ID=3764988

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1727773A Expired GB1397014A (en) 1972-04-13 1973-04-10 Fabrication process for nuclear fuel pellets

Country Status (2)

Country Link
CA (1) CA1009434A (en)
GB (1) GB1397014A (en)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2379885A1 (en) * 1977-02-04 1978-09-01 Westinghouse Electric Corp ARRANGEMENT FOR THE MANUFACTURE OF NUCLEAR FUEL PELLETS
DE2816141A1 (en) * 1977-04-29 1978-11-02 Westinghouse Electric Corp TEST DEVICE FOR NUCLEAR FUEL TABLETS
FR2506497A1 (en) * 1981-05-19 1982-11-26 British Nuclear Fuels Ltd PROCESS FOR MANUFACTURING NUCLEAR FUEL PELLETS AND PELLET THUS FORMED
GB2127735A (en) * 1982-07-21 1984-04-18 Atomic Energy Authority Uk Extruding loose (particulate) material into coherent bodies
EP0840330A1 (en) * 1996-11-01 1998-05-06 General Electric Company Segmented pellet and production thereof
US5916497A (en) * 1994-12-16 1999-06-29 British Nuclear Fuels Plc Manufacturing of ceramic articles
WO2000045394A1 (en) * 1999-01-26 2000-08-03 Belgonucleaire Sa Method for dry process recycling of mixed (u, pu)o2 oxide nuclear fuel waste

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2379885A1 (en) * 1977-02-04 1978-09-01 Westinghouse Electric Corp ARRANGEMENT FOR THE MANUFACTURE OF NUCLEAR FUEL PELLETS
DE2816141A1 (en) * 1977-04-29 1978-11-02 Westinghouse Electric Corp TEST DEVICE FOR NUCLEAR FUEL TABLETS
FR2506497A1 (en) * 1981-05-19 1982-11-26 British Nuclear Fuels Ltd PROCESS FOR MANUFACTURING NUCLEAR FUEL PELLETS AND PELLET THUS FORMED
GB2127735A (en) * 1982-07-21 1984-04-18 Atomic Energy Authority Uk Extruding loose (particulate) material into coherent bodies
US5916497A (en) * 1994-12-16 1999-06-29 British Nuclear Fuels Plc Manufacturing of ceramic articles
EP0840330A1 (en) * 1996-11-01 1998-05-06 General Electric Company Segmented pellet and production thereof
WO2000045394A1 (en) * 1999-01-26 2000-08-03 Belgonucleaire Sa Method for dry process recycling of mixed (u, pu)o2 oxide nuclear fuel waste
US6783706B1 (en) 1999-01-26 2004-08-31 Belgonucleaire Sa Method for dry process recycling of mixed (U,Pu)O2 oxide nuclear fuel waste

Also Published As

Publication number Publication date
CA1009434A (en) 1977-05-03

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee