Zobrazeno 1 - 8 of 8 pro vyhledávání: '"O. T. Woo"'
1
Effect of Pressures on the Corrosion Behaviours of Materials at 625°C
Autor: R. Sanchez, Xiao Huang, W. Li, O. T. Woo, C. D. Bibby, J. Li
Publikováno v: JOM. 69:207-216
The corrosion behaviors of austenitic stainless steels (SS) 310, 304 and Ni- and Fe-based A-286 exposed to 0.1 MPa, 8 MPa and 29 MPa at 625°C for 1000 h were investigated. These represent exposure to superheated steam, subcritical and supercritical
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::2df2009c6d912d5d2b6df507aaaef35b
https://doi.org/10.1007/s11837-016-2201-x
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4
A replica technique for extracting precipitates from zirconium alloys for transmission electron microscopy analysis
Autor: J. Ng-Yelim, O. T. Woo, G. J. C. Carpenter
Publikováno v: Journal of Electron Microscopy Technique. 15:400-405
A reliable two-stage carbon replica technique has been developed to extract precipitates from zirconium alloys. Using this technique, all precipitating phases can be extracted from Zircaloy-2, Zr-Cr-Fe, and Zr-Nb-Fe alloys. Precipitate identification
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d649b36b2bdd10ce9c1e95cef15b012a
https://doi.org/10.1002/jemt.1060150410
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5
Improved Zr-2.5Nb Pressure Tubes for Reduced Diametral Strain in Advanced CANDU Reactors
Autor: G. A. Bickel, M. Griffiths, A. Douchant, S. Douglas, O. T. Woo, A. Buyers, P. Barberis, S. W. Dean
Publikováno v: Journal of ASTM International. 8:103521
In an Advanced CANDU Reactor (ACR) (ACR is a registered trademark of Atomic Energy of Canada Limited), pressure tubes of cold-worked Zr-2.5Nb materials will be used in the reactor core to contain the fuel bundles and the light water coolant. They wil
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9c86c6c7bd8fad549655cbf00e6b4230
https://doi.org/10.1520/jai103521
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6
Deformation of α-zirconium in the vicinity of 0.5 tinm
Autor: R. G. Fleck, O. T. Woo, E. T. C. Ho, S. R. Macewen
Publikováno v: Metallurgical Transactions A. 12:1751-1759
The creep behavior of specimens of α-Zr, machined from the three principal directions of a rolled slab or from swaged rod, has been studied in the temperature range 870 to 975 K, for stresses in the range 5 to 20 MPa. For a given stress and temperat
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::f66f23f60b1544640abce65c6a53e341
https://doi.org/10.1007/bf02643757
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8
Effect of pressure on the corrosion of materials in high temperature water
Autor: W. Li, Xiao Huang, O. T. Woo, C. D. Bibby, Rainier Garcia Sanchez, David Guzonas, J. Li
Publikováno v: Scopus-Elsevier
Characterization of Minerals, Metals, and Materials 2015 ISBN: 9783319486017
Characterization of Minerals, Metals, and Materials 2015
One of the major challenges for the Canadian Gen IV Super-Critical Water-cooled Reactor (SCWR) concept is the selection of fuel cladding materials. The Canadian SCWR concept will operate at a core outlet temperature of 625 °C and 25 MPa of pressure
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a8008f65475ed4724be9ddb5ea2b5c08
http://www.scopus.com/inward/record.url?eid=2-s2.0-84937030163&partnerID=MN8TOARS
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