Carbon diffusion in bulk hcp zirconium: A multi-scale approach

Y. Xu (1, 2) , J. Roques (1) , C. Domain (2) , E. Simoni (1)

1 IPNO - Institut de Physique Nucléaire d'Orsay
2 EDF R&D MMC - Matériaux et Mécanique des Composants

In the framework of the geological repository of the used fuel claddings of pressurized water reactor, carbon behavior in bulk zirconium is studied by periodic Density Functional Theory calculations. The C interstitial sites were investigated and it was found that there are two possible carbon interstitial sites: a distorted basal tetragonal site and an octahedral site. There are four types of possible atomic jumps between them. After calculating the migration energies, the attempt frequencies and the jump probabilities for each possible migration path, kinetic Monte Carlo (KMC) simulations were performed to simulate carbon diffusion at the macroscopic scale. The results show that carbon diffusion in pure Zr bulk is extremely limited at the storage temperature (50 °C). Since there are defects in Zr bulk, in a second step, the effect of atomic vacancy was studied and it was proved that vacancies cannot increase carbon diffusion.

Domaines: Chimie-Physique [physics.chem-ph]

Y. Xu, J. Roques, C. Domain, E. Simoni. Carbon diffusion in bulk hcp zirconium: A multi-scale approach. Journal of Nuclear Materials, 2016, 473, pp.61-67. ⟨10.1016/j.jnucmat.2016.02.010⟩. ⟨in2p3-01339312⟩