[go: up one dir, main page]
More Web Proxy on the site http://driver.im/

Chotard et al., 1991 - Google Patents

Fabrication, Characteristics and in-Pile Performance of UO2 Pellets Prepared from Dry Route Powder

Chotard et al., 1991

Document ID
10326015655262767726
Author
Chotard A
Ledac A
Bernardin M
Publication year
Publication venue
Key Engineering Materials

External Links

Snippet

Copyright Trans Tech Publications, Switzerland Page 1 Key Engineering Materials Vols. 56-57 (1991) pp 471-488 © (1991) Trans Tech Publications, Switzerland doi: 10.4028/www. scientific. net/KEM. 56-5 7 4 71 Key Engineering Materials Vols. 56 - 57 (IWI)pp. 471-4ÜH Copyright Trans …
Continue reading at www.scientific.net (other versions)

Classifications

    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/38—Fuel
    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/40—Other aspects relating to nuclear fission
    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E60/00—Enabling technologies or technologies with a potential or indirect contribution to GHG emissions mitigation
    • Y02E60/50—Fuel cells
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium

Similar Documents

Publication Publication Date Title
CA2254489C (en) Method of manufacturing nuclear fuel pellet by recycling irradiated oxide fuel pellet
Ganguly et al. Development and fabrication of 70% PuC–30% UC fuel for the fast breeder test reactor in India
US6808656B2 (en) Method of producing a nuclear fuel sintered body
KR19990004218A (en) How to recycle defective products of oxide fueled sintered body
CA1107054A (en) Process for the production of ceramic plutonium uranium nuclear fuel in the form of sintered pellets
KR20040029408A (en) Method for producing a mixed oxide nuclear fuel powder and a mixed oxide nuclear fuel sintered compact
Dörr et al. Study of the formation of UO2-PuO2 solid solution by means of UO2-CeO2 simulate
KR101302695B1 (en) Fabrication method of burnable absorber nuclear fuel pellet, and the burnable absorber nuclear fuel pellet thereby
US3715273A (en) Nuclear fuel element containing sintered uranium dioxide fuel with a fine particulate dispersion of an oxide additive therein,and method of making same
Ayaz et al. The possible usage of ex-ADU uranium dioxide fuel pellets with low-temperature sintering
Chotard et al. Fabrication, Characteristics and in-Pile Performance of UO2 Pellets Prepared from Dry Route Powder
Bernard Advanced fuel fabrication
US3270098A (en) Method of making hollow, spherical uo2 particles
KR100331483B1 (en) Method of manufacturing oxide fuel pellets containing neutron-absorbing materials
JP4674312B2 (en) Nuclear fuel pellet manufacturing method and nuclear fuel pellet
RU2679117C1 (en) Method for obtaining ceramic nuclear fuel
Richter et al. Direct pressing: a new method of fabricating MX fuel pellets
US3761546A (en) Method of making uranium dioxide bodies
Mukerjee et al. Fabrication technologies for ThO2-based fuel
JP2701043B2 (en) Method for producing oxide nuclear fuel body having double microstructure
KR100969644B1 (en) A fabrication method of nuclear fuel pellet by using high burnup spent nuclear fuel
JP2701049B2 (en) Method for producing oxide nuclear fuel body by air sintering
US3294698A (en) Hollow, spherical uo2 nuclear fuel particles
SHOUP Process variables in the preparation of UN microspheres
JPH0761820A (en) Production of nuclear fuel pellet