Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7966931 | Journal of Nuclear Materials | 2015 | 9 Pages |
Abstract
The paper deals with high-temperature steam oxidation behaviour of Zr1Nb fuel cladding. First of all, comprehensive experimental program was conducted to provide sufficient experimental data, such as the thicknesses of evolved phase layers and the overall weight gain kinetics, as well as the oxygen concentration and nanohardness values at phase boundaries. Afterwards, oxygen diffusion coefficients in the oxide, in the α-Zr(O) layer, in the double-phase (α + β)-Zr region, and in the β-phase region have been estimated based on the experimental data employing analytical solution of the multiphase moving boundary problem, assuming the equilibrium conditions being fulfilled at the interface boundaries. Eventually, the determined oxygen diffusion coefficients served as input into the in-house numerical code, which was designed to predict the high-temperature oxidation behaviour of Zr1Nb fuel cladding. Very good agreement has been achieved between the numerical calculations and the experimental data.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
M. Négyesi, T. Chmela, T. Veselský, J. KrejÄÃ, L. Novotný, A. PÅibyl, O. Bláhová, J. Burda, J. Siegl, V. VrtÃlková,