TY - JOUR
T1 - Mechanism of neutron irradiation-induced surface crack density changes in Chromium-coated zirconium alloys
AU - Han, Mingda
AU - Zhang, Weixu
AU - Lv, Junnan
AU - Yang, Hongyan
AU - Jiang, Jishen
N1 - Publisher Copyright:
© 2025 Elsevier B.V.
PY - 2025/9
Y1 - 2025/9
N2 - This study investigates the effect of irradiation on the crack density of chromium-coated zirconium alloys. Based on the continuum mechanics framework, irradiation damage is described through changes in the stress-strain curve. A fracture prediction method for chromium coatings is established using a strength theory and the birth and death element method, showing good agreement with experimental trends. The study shows that with increasing irradiation dose, the substrate material undergoes irradiation-induced embrittlement, leading to a significant increase in interfacial shear stress. As a result, the initial cracking strain decreases from approximately 0.414 % to 0.408 %, the saturated crack density increases by about 36.4 %, and the crack opening displacement decreases by around 36.6 %. For coating thickness, a thicker coating leads to a lower saturated crack density. When the substrate thickness exceeds the critical value, it no longer affects the saturated crack density. The residual stress in the coating does not affect the saturated crack density but only influences the crack initiation strain. This study provides theoretical support for the irradiation-resistant design of accident-tolerant fuel cladding coatings.
AB - This study investigates the effect of irradiation on the crack density of chromium-coated zirconium alloys. Based on the continuum mechanics framework, irradiation damage is described through changes in the stress-strain curve. A fracture prediction method for chromium coatings is established using a strength theory and the birth and death element method, showing good agreement with experimental trends. The study shows that with increasing irradiation dose, the substrate material undergoes irradiation-induced embrittlement, leading to a significant increase in interfacial shear stress. As a result, the initial cracking strain decreases from approximately 0.414 % to 0.408 %, the saturated crack density increases by about 36.4 %, and the crack opening displacement decreases by around 36.6 %. For coating thickness, a thicker coating leads to a lower saturated crack density. When the substrate thickness exceeds the critical value, it no longer affects the saturated crack density. The residual stress in the coating does not affect the saturated crack density but only influences the crack initiation strain. This study provides theoretical support for the irradiation-resistant design of accident-tolerant fuel cladding coatings.
KW - Coating/substrate thickness
KW - Neutron irradiation
KW - Random defects
KW - Residual stress
KW - Strength theory
KW - Surface crack density
UR - https://www.scopus.com/pages/publications/105008406330
U2 - 10.1016/j.jnucmat.2025.155982
DO - 10.1016/j.jnucmat.2025.155982
M3 - 文章
AN - SCOPUS:105008406330
SN - 0022-3115
VL - 615
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 155982
ER -