TY - GEN
T1 - TEM examinations of the metal-oxide interface of zirconium based alloys irradiated in a pressurized water reactor
AU - Abolhassani, S.
AU - Restani, R.
AU - Rebac, T.
AU - Groeschel, F.
AU - Hoffelner, W.
AU - Bart, G.
AU - Goll, W.
AU - Aeschbach, F.
AU - Cox, B.
AU - Kammenzind, B.
AU - Cheng, B.
AU - Motta, A.
PY - 2005
Y1 - 2005
N2 - Metal-oxide interfaces of three different materials irradiated in a pressurized water reactor have been analyzed by TEM and AEM. Standard Zircaloy-4, low-tin Zircaloy-4, and Zr-2.5%Nb were used for this study. The microstructure of the material on the two sides of the metal-oxide interface, the geometry of the interface, the distribution of different alloying elements, and the oxygen profile have been examined in each material. Results of the examinations showed that the three materials had different microstructure and oxygen distribution on the two sides of the metal-oxide interface. In particular, the following parameters were noticed: a) the geometry of the interface seems to be of a different nature in the case of Zr-2.5%Nb alloy. Unlike the Zircaloy-4 alloys, which show an undulated interface, this material has a "jigsaw" type interface. This point is discussed, and its role on the oxidation is considered, b) Hydrides are observed and analyzed in the vicinity of the interface in the case of low-tin Zircaloy-4, and it is shown that they can have an influence on the occurrence of cracks in this material. c) The origins of stress are discussed, and it is shown that it can have different sources. The crystal structure of the oxides is mainly monoclinic. A tetragonal oxide is observed at some regions, in particular in the standard Zircaloy-4.
AB - Metal-oxide interfaces of three different materials irradiated in a pressurized water reactor have been analyzed by TEM and AEM. Standard Zircaloy-4, low-tin Zircaloy-4, and Zr-2.5%Nb were used for this study. The microstructure of the material on the two sides of the metal-oxide interface, the geometry of the interface, the distribution of different alloying elements, and the oxygen profile have been examined in each material. Results of the examinations showed that the three materials had different microstructure and oxygen distribution on the two sides of the metal-oxide interface. In particular, the following parameters were noticed: a) the geometry of the interface seems to be of a different nature in the case of Zr-2.5%Nb alloy. Unlike the Zircaloy-4 alloys, which show an undulated interface, this material has a "jigsaw" type interface. This point is discussed, and its role on the oxidation is considered, b) Hydrides are observed and analyzed in the vicinity of the interface in the case of low-tin Zircaloy-4, and it is shown that they can have an influence on the occurrence of cracks in this material. c) The origins of stress are discussed, and it is shown that it can have different sources. The crystal structure of the oxides is mainly monoclinic. A tetragonal oxide is observed at some regions, in particular in the standard Zircaloy-4.
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M3 - Conference contribution
AN - SCOPUS:33744786260
SN - 0803134932
SN - 9780803134935
T3 - ASTM Special Technical Publication
SP - 467
EP - 493
BT - Zirconium in the NUCLEAR INDUSTRY - Fourteenth International Symposium
PB - American Society for Testing and Materials
T2 - 14th International Symposium on Zirconium in the NUCLEAR INDUSTRY
Y2 - 13 June 2004 through 17 June 2004
ER -