TY - JOUR
T1 - Mechanical–chemical coupling phase-field modeling for inhomogeneous oxidation of zirconium induced by stress–oxidation interaction
AU - Lin, Chen
AU - Ruan, Haihui
AU - Shi, San Qiang
N1 - Funding Information:
H.H.R. acknowledges the support of the Early Career Scheme (ECS) of the Hong Kong Research Grants Council (Grant No. 25200515, Account Code F-PP27) and the departmental General Research Funds (G-YBMK) of Hong Kong Polytechnic University. S.Q.S. acknowledges the support from the National Natural Science Foundation of China (No. 51672232) and from Hong Kong Polytechnic University under Grant No. 1-99QP. C.L. acknowledges the support from Natural Science Basic Research Plan in Shaanxi Province of China (No. 2019JQ-123). We are grateful for this support.
Publisher Copyright:
© 2020, The Author(s).
PY - 2020/12
Y1 - 2020/12
N2 - A phase-field model is proposed to study the inhomogeneous growth of zirconia induced by the stress–oxidation interaction, which captures the complex interplay among diffusion, oxidation kinetics, interfacial morphology evolution, and stress variation in an oxidation process. Through this numerical model, many experimentally observed but insufficiently understood phenomena can be well explained. Specifically, the numerical simulations reveal quantitatively the causes of interface roughening or smoothening during the inward oxide growth, the roughness-dependent oxide growth rate, and the nucleation sites of premature cracking. These numerical findings can be used as the theoretical references for the improving the durability of oxide scale and prolonging the service life of zirconium-based alloy cladding used in the nuclear power plant.
AB - A phase-field model is proposed to study the inhomogeneous growth of zirconia induced by the stress–oxidation interaction, which captures the complex interplay among diffusion, oxidation kinetics, interfacial morphology evolution, and stress variation in an oxidation process. Through this numerical model, many experimentally observed but insufficiently understood phenomena can be well explained. Specifically, the numerical simulations reveal quantitatively the causes of interface roughening or smoothening during the inward oxide growth, the roughness-dependent oxide growth rate, and the nucleation sites of premature cracking. These numerical findings can be used as the theoretical references for the improving the durability of oxide scale and prolonging the service life of zirconium-based alloy cladding used in the nuclear power plant.
UR - http://www.scopus.com/inward/record.url?scp=85105890869&partnerID=8YFLogxK
U2 - 10.1038/s41529-020-00125-6
DO - 10.1038/s41529-020-00125-6
M3 - Journal article
AN - SCOPUS:85105890869
SN - 2397-2106
VL - 4
JO - npj Materials Degradation
JF - npj Materials Degradation
IS - 1
M1 - 22
ER -