CA1063338A - Method of fabricating nuclear fuel - Google Patents

Method of fabricating nuclear fuel

Info

Publication number
CA1063338A
CA1063338A CA247,800A CA247800A CA1063338A CA 1063338 A CA1063338 A CA 1063338A CA 247800 A CA247800 A CA 247800A CA 1063338 A CA1063338 A CA 1063338A
Authority
CA
Canada
Prior art keywords
additive
fuel
nuclear fuel
solvent
compact
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
CA247,800A
Other languages
English (en)
French (fr)
Inventor
Harvey R. Lee
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.)
General Electric Canada Co
Original Assignee
Canadian General Electric Co Ltd
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 Canadian General Electric Co Ltd filed Critical Canadian General Electric Co Ltd
Priority to CA247,800A priority Critical patent/CA1063338A/en
Priority to GB9251/77A priority patent/GB1557904A/en
Priority to US05/774,928 priority patent/US4110159A/en
Priority to FR7706709A priority patent/FR2344096A1/fr
Priority to JP2615077A priority patent/JPS52110395A/ja
Application granted granted Critical
Publication of CA1063338A publication Critical patent/CA1063338A/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
    • C04B41/00After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
    • C04B41/009After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone characterised by the material treated
    • 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
    • C04B41/00After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
    • C04B41/45Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements
    • C04B41/50Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements with inorganic materials
    • 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
    • C04B41/00After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
    • C04B41/80After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone of only ceramics
    • C04B41/81Coating or impregnation
    • C04B41/85Coating or impregnation with inorganic materials
    • 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
    • G21C3/60Metallic fuel; Intermetallic dispersions
    • 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
    • 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

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Ceramic Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Organic Chemistry (AREA)
  • Structural Engineering (AREA)
  • Materials Engineering (AREA)
  • Inorganic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Dispersion Chemistry (AREA)
  • Liquid Carbonaceous Fuels (AREA)
CA247,800A 1976-03-12 1976-03-12 Method of fabricating nuclear fuel Expired CA1063338A (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
CA247,800A CA1063338A (en) 1976-03-12 1976-03-12 Method of fabricating nuclear fuel
GB9251/77A GB1557904A (en) 1976-03-12 1977-03-04 Process for manufacturing a nuclear fuel body
US05/774,928 US4110159A (en) 1976-03-12 1977-03-07 Method of fabricating nuclear fuel
FR7706709A FR2344096A1 (fr) 1976-03-12 1977-03-08 Combustible nucleaire perfectionne
JP2615077A JPS52110395A (en) 1976-03-12 1977-03-11 Nuclear fuel for power reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA247,800A CA1063338A (en) 1976-03-12 1976-03-12 Method of fabricating nuclear fuel

Publications (1)

Publication Number Publication Date
CA1063338A true CA1063338A (en) 1979-10-02

Family

ID=4105451

Family Applications (1)

Application Number Title Priority Date Filing Date
CA247,800A Expired CA1063338A (en) 1976-03-12 1976-03-12 Method of fabricating nuclear fuel

Country Status (5)

Country Link
US (1) US4110159A (enExample)
JP (1) JPS52110395A (enExample)
CA (1) CA1063338A (enExample)
FR (1) FR2344096A1 (enExample)
GB (1) GB1557904A (enExample)

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SE7701017L (sv) * 1976-03-25 1977-09-26 Ca Atomic Energy Ltd Blandoxidkernbrensle
JPH03137596A (ja) * 1989-10-23 1991-06-12 Nuclear Fuel Ind Ltd 核燃料ペレット
US5112534A (en) * 1990-03-05 1992-05-12 The United States Of America As Represented By The United States Department Of Energy Yttrium and rare earth stabilized fast reactor metal fuel
US5242631A (en) * 1992-01-13 1993-09-07 Westinghouse Electric Corp. Method for coating nuclear fuel pellets
US7666470B1 (en) * 2003-10-24 2010-02-23 Areva Np Inc. Process for manufacturing enhanced thermal conductivity oxide nuclear fuel and the nuclear fuel
US8571167B2 (en) * 2009-06-01 2013-10-29 Advanced Reactor Concepts LLC Particulate metal fuels used in power generation, recycling systems, and small modular reactors
US9793013B2 (en) * 2009-11-06 2017-10-17 Terrapower, Llc Systems and methods for controlling reactivity in a nuclear fission reactor
US9852818B2 (en) * 2009-11-06 2017-12-26 Terrapower, Llc Systems and methods for controlling reactivity in a nuclear fission reactor
US9190177B2 (en) * 2009-11-06 2015-11-17 Terrapower, Llc Systems and methods for controlling reactivity in a nuclear fission reactor
CN102714065B (zh) * 2009-11-06 2016-08-24 泰拉能源有限责任公司 用于控制核反应堆中的反应性的系统和方法
KR102025676B1 (ko) 2010-09-03 2019-09-26 아토믹 에너지 오브 캐나다 리미티드 토륨을 함유하는 핵연료 다발 및 그것을 포함하는 원자로
US10950356B2 (en) 2010-11-15 2021-03-16 Atomic Energy Of Canada Limited Nuclear fuel containing recycled and depleted uranium, and nuclear fuel bundle and nuclear reactor comprising same
RO129195B1 (ro) 2010-11-15 2019-08-30 Atomic Energy Of Canada Limited Combustibil nuclear conţinând un absorbant de neutroni

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL299042A (enExample) * 1962-10-10
US3427222A (en) * 1965-10-15 1969-02-11 Westinghouse Electric Corp Nuclear fuel elements
GB1208433A (en) * 1967-04-20 1970-10-14 Atomic Energy Authority Uk Manufacture of ceramic artefacts having pores
US3514412A (en) * 1967-09-25 1970-05-26 Grace W R & Co Process for preparing urania-plutonia nuclear fuel
US3933582A (en) * 1968-09-26 1976-01-20 General Electric Company Plutonium fuel adjacent burnable poison
US3917768A (en) * 1969-02-25 1975-11-04 Fiat Spa Sintered nuclear fuel and method of preparing same
BE743232A (enExample) * 1969-02-25 1970-05-28

Also Published As

Publication number Publication date
JPS52110395A (en) 1977-09-16
FR2344096B1 (enExample) 1981-01-16
US4110159A (en) 1978-08-29
FR2344096A1 (fr) 1977-10-07
GB1557904A (en) 1979-12-12

Similar Documents

Publication Publication Date Title
CA1063338A (en) Method of fabricating nuclear fuel
US4020131A (en) Preparation of mixed oxide nuclear fuel
US4774051A (en) Sintered nuclear fuel compact and method for its production
KR20180059399A (ko) 국부의 가연성흡수체를 포함하는 핵연료 소결체
US5642390A (en) Uranium-containing nuclear-fuel sintered pellet
EP3192076B1 (en) Method of making a nuclear fuel pellet for a nuclear power reactor
Lahr Fabrication, properties, and irradiation behavior of U/Pu particle fuel for light water reactors
US3087879A (en) Control rod
US20200111584A1 (en) Composite fuel with enhanced oxidation resistance
DE1464625A1 (de) Hochtemperatur-Kernreaktor
US20010022827A1 (en) Nuclear reactor fuel assembly with a high burnup
Young et al. The low-energy total neutron cross section of plutonium-242
US4557861A (en) Nuclear fuel cartridge, and a method of preparing the cartridge for the extraction of nuclear material therefrom
Bremier et al. Fission gas release and fuel swelling at burn-ups higher than 50 MWd/kgU
US3219541A (en) Method of preventing carburization of fuel element cladding metals by uranium carbide fuels
DE1804378A1 (de) Kernbrennstoffstaebe mit Huellrohr
Roland et al. A new basket for transport storage casks
Nabielek KFA Contribution to LEU Fuel Performance Review. Critical Evaluation of Low Enriched Uranium Fuel Performance Data
Ninokata et al. A study on recriticality characteristics of fast reactors in pursuit of recriticality-accident-free concepts
JPS54150582A (en) Fuel assembly
EP0026573A1 (en) A mixed oxide fuel pellet for use in a nuclear reactor and a method of manufacturing such a pellet
Roepenack et al. IAEA SPECIALISTS'MEETING ON IWPROVED UTILIZATION OF:/I-WATER REACTOR FUEL WITH SPECIAL EMPHASIS ON EXTENDED
Lawrence et al. Actinide redistribution in the outer regions of mixed-oxide fuel
Brunet MARIUS IV: a critical experiments programme on CGA type lattices
Zimmermann Fission gas behaviour in UO2 under steady state and transient conditions