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Rhee, Young Woo; Kim, Dong Joo; Kim, Jong Hun; Yang, Jae Ho; Kim, Keon Sik; Kang, Ki Won; Song, Kun Woo
Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors. Additional Information2010
Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors. Additional Information2010
AbstractAbstract
No abstract available
Primary Subject
Source
International Atomic Energy Agency, Nuclear Fuel Cycle and Materials Section, Vienna (Austria); [CD]; ISBN 978-92-0-108910-6;
; ISSN 1011-4289;
; Oct 2010; 33 p; Technical Committee Meeting on Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors; Villigen (Switzerland); 23-26 Nov 2009; Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/TE_1654_companion_CD/Start.pdf and attached to the printed IAEA-TECDOC-1654; Orders and requests for information may be addressed directly to IAEA, Sales and Promotion Unit: E-mail: sales.publications@iaea.org; Web site: http://www.iaea.org/books; PowerPoint presentation


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AbstractAbstract
No abstract available
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Letter-to-the-editor.
Record Type
Journal Article
Journal
Revue Roumaine de Physique; v. 21(2); p. 217-220
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AbstractAbstract
No abstract available
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Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
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Journal Article
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Conference
Journal
Transactions of the American Nuclear Society; v. 24 p. 375-376
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AbstractAbstract
No abstract available
Original Title
Patent
Primary Subject
Source
30 Apr 1974; 4 p; US PATENT DOCUMENT 3,808,099
Record Type
Patent
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Bujas, Roko.
CEA, 75 - Paris (France)1971
CEA, 75 - Paris (France)1971
AbstractAbstract
No abstract available
Original Title
Support de cartouche combustible pour reacteur nucleaire
Primary Subject
Source
25 May 1971; 6 p; FR PATENT DOCUMENT 2138411/A/; Available from INPI, Paris; Available from Institut National de la Propriete Industrielle, Paris (France).
Record Type
Patent
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AbstractAbstract
No abstract available
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Source
American Nuclear Society's annual meeting; Miami Beach, FL (USA); 7 - 12 Jun 1981; CONF-810606--; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; ISSN 0003-018X;
; v. 38 p. 149-150

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Bergeron, A.; Hamilton, H.
CANDU fuel : safe, reliable and flexible. 12th international conference on CANDU fuel2013
CANDU fuel : safe, reliable and flexible. 12th international conference on CANDU fuel2013
AbstractAbstract
[en] Annular pellets are a variant of the standard solid cylindrical pellet, the difference being the presence of a void along the cylindrical axis. Fabrication of such pellets is common and methods are well understood. Internally cooled annular fuel (ICAF) uses annular pellets clad both externally and internally so that coolant can flow through the centre as well as around the outside of the element. In order to maximize the heat transfer to the coolant flowing through the centre, the gap between the inside diameter of the pellet and the inner cladding must be minimized. This paper describes fabrication development efforts towards producing annular pellets with precise and accurate inside diameters in order to minimize the pellet-inner cladding gap for internally cooled annular fuel. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); 242 Megabytes; ISBN 978-1-926773-14-8;
; 2013; [12 p.]; 12. International conference on CANDU fuel; Kingston, Ontario (Canada); 15-18 Sep 2013; Available as slide presentation also.; Available from the Canadian Nuclear Society, 480 University Avenue, Suite 200, Toronto, Ontario, Canada; 6 refs.; 2 tabs.; 8 figs.

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AbstractAbstract
[en] A fuel element assembly for a high temperature reactor comprises a prismatic block having fuel containing bores and interstitial coolant conducting bores extending end-to-end. The fuel comprises stacks of annular compacts which line the fuel containing bores and define central coolant flow channels through the fuel. (U.S.)
Original Title
Patent; HTGR
Primary Subject
Source
25 Mar 1975; 2 p; US PATENT DOCUMENT 3,873,420
Record Type
Patent
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Ballagny, Alain.
CEA, 75 - Paris (France)1971
CEA, 75 - Paris (France)1971
AbstractAbstract
No abstract available
Original Title
Element combustible pour reacteur nucleaire
Primary Subject
Source
25 Jun 1971; 6 p; FR PATENT DOCUMENT 2142823/A/; Available from INPI, Paris; Available from Institut National de la Propriete Industrielle, Paris (France).
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
18 Sep 1974; 4 p; GB PATENT DOCUMENT 1367352/B/
Record Type
Patent
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