Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms 250, 95–100 (2006).
Simeone, D., Baldinozzi, G., Gosset, D., LeCaër, S. International Atomic Energy Agency (IAEA) (1999) Gibert, F., Couvreur, C., Damien, D., Gautier-Soyer, M., Thromat, N., Guittet, M.J., Serruys, Y., Bouffard, S. Zhang, Y., Jiang, W., Wang, C., Namavar, F., Edmondson, P.D., Zhu, Z., Gao, F., Lian, J. Polatidis, E., Frankel, P., Wei, J., Klaus, M., Comstock, R.J., Ambard, A., Lyon, S., Cottis, R.A. 18th International Symposium on Zirconium in the Nuclear Industry ASTM International (2018) Garner, A., Baxter, F., Frankel, P., Topping, M., Harte, A., Slater, T., Tejland, P., Romero, J., Darby, Cole-Baker, A., Gass, M. International Atomic Energy Agency (IAEA), Corrosion of zirconium alloys in nuclear power plants, IAEA-TECDOC-684, IAEA, Vienna (1992). Garner, A., Gholinia, A., Frankel, P., Gass, M., MacLaren, I. Liao, J., Yang, Z., Qiu, S., Peng, Q., Li, Z. Liu, J., He, G., Hu, J., Shen, Z., Kirk, M., Li, M., Ryan, E., Baldo, P., Lozano-Perez, S. Hu, J., Garner, A., Frankel, P., Li, M., Kirk, M.A., Lozano-Perez, S., Preuss, M. Nuclear Engineering and Technology 50, 259–267 (2018). Lach, T.G., Edwards, D.J., Buck, E.C., McNamara, B.K., Schwantes, J.M. Journal of Raman Spectroscopy 50, 425–435 (2019).Ĭiszak, C., Desgranges, L., Garcia, P., Sabathier, C., Fayette, L. Journal of Nuclear Materials 495, 392–404 (2017).Ĭiszak, C., Mermoux, M., Gutierrez, G., Leprêtre, F., Duriez, C., Popa, I., Fayette, L. The ZrO 2 in contact with the fuel is more developed in this case than in the medium-burnup sample, but it shows the same microstructure.Ĭiszak, C., Mermoux, M., Miro, S., Gutierrez, G., Lepretre, F., Popa, I., Hanifi, K., Zacharie-Aubrun, I., Fayette, L. In the high-burnup sample (61 GWd/tU), zirconia presents a wavy interface with some circumvolutions. Thereafter, two intermediate zones can be observed: a first composed of very small equiaxed grains and a second with a mixture of intermediate and large grains. In the medium-burnup sample (37 GWd/tU), the zirconia in the first zone in contact with the cladding exhibits the same kind of microstructure as ‘ordinary’ zirconium oxide formed on the cladding outer surface, which is characterized by columnar and equiaxed grains. Four different zones can be distinguished in the zirconia layer of each sample.
The development of internal zirconia is, however, constrained mechanically by the contact of the UO 2 fuel. It seems that the zirconia develops ‘normally’ until it comes into contact with the fuel. This paper analyzes the microstructure of zirconia formed at the Zr cladding/UO 2 interface in two samples with different burnups. The inner surface of the Zr cladding in contact with the UO 2 fuel therefore oxidizes. See all condition definitions - opens in a new window or tabĨ1001700 AJUSA 81008700 AJUSA B006DJO3HS AMAZON (ASIN), 820 490 ARTNR_Z_TCD 016222B CORTECO 9501660 GLASER, 55P IC 22-18083B IC 820474 IC HBS 001 PAYEN, 480-1003082 CHERY 6 083 155 FORD, Cylinder head bolt kit FORD ESCORT '81 EXPRESS, ESCORT '86 EXPR, ESS, ESCORT '91 EXPRESS, ESCORT '95, ESCORT III, ESCORT IV, ESC, ORT V, ESCORT VI, FIESTL, FIESTL II, FIESTL III 1.1-1.6 09.80-0, 8.During irradiation in a nuclear reactor, the UO 2 fuel and the Zr cladding come into contact due to fuel thermal expansion and cladding creep.
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