TY - JOUR
T1 - Growth inertia of irradiation defects and its governing role in microstructural evolution in Mo-Re alloys
AU - Cui, Dewang
AU - Yang, Tian Ren
AU - Cao, Ziqi
AU - Liao, Jingjing
AU - Qiu, Xi
AU - Wang, Yiwei
AU - Zhang, Wei
AU - Li, Yuanming
AU - Dai, Xun
AU - Li, Quan
AU - Sun, Chao
AU - Li, Chengen
AU - Li, Yu Hao
AU - Zhou, Hong Bo
AU - Ran, Guang
N1 - Publisher Copyright:
© 2026
PY - 2026/12/10
Y1 - 2026/12/10
N2 - Microstructural evolution under temperature fluctuations during irradiation is strongly history-dependent. Early-stage irradiation defects can act as sinks that bias later evolution, but the conditions that let these sinks remain dominant are unclear, limiting reliable prediction of defect evolution under realistic service conditions. Here, by combining in-situ temperature-varying irradiation with object kinetic Monte Carlo (OKMC) simulations, this study identifies a growth-inertia effect of early-formed defects, in which irradiation defects tend to inherit their prior growth behavior even under drastic temperature reduction. Two critical thresholds define the stability of this inertial regime: a critical failure temperature Tc (∼400–500 °C, ∼450 °C as an estimate for Mo-5Re-0.5Nb) and a critical initial dose Dc (∼0.015 dpa). When the temperature falls below Tc and/or the initiation dose is below Dc, growth inertia breaks down, leading to substantial defect re-nucleation. A dimensionless kinetic descriptor, termed inertia potential Q, was derived from defect kinetics to quantify the underlying mechanisms. The generality of growth inertia was examined in both Mo-based alloys and pure Mo, with pure Mo exhibiting a lower Tc (∼300–400 °C), consistent with OKMC simulation predictions that Q decreases with increasing Re content. Furthermore, when a sufficient initiation dose (above Dc) is provided, high-temperature pre-irradiation suppresses subsequent nucleation at lower temperatures, yielding a sparse large-loop microstructure with reduced irradiation hardening. These findings establish defect initiation as a governing factor in irradiation evolution and provide a quantitative framework for predicting microstructural stability under variable-temperature irradiation conditions.
AB - Microstructural evolution under temperature fluctuations during irradiation is strongly history-dependent. Early-stage irradiation defects can act as sinks that bias later evolution, but the conditions that let these sinks remain dominant are unclear, limiting reliable prediction of defect evolution under realistic service conditions. Here, by combining in-situ temperature-varying irradiation with object kinetic Monte Carlo (OKMC) simulations, this study identifies a growth-inertia effect of early-formed defects, in which irradiation defects tend to inherit their prior growth behavior even under drastic temperature reduction. Two critical thresholds define the stability of this inertial regime: a critical failure temperature Tc (∼400–500 °C, ∼450 °C as an estimate for Mo-5Re-0.5Nb) and a critical initial dose Dc (∼0.015 dpa). When the temperature falls below Tc and/or the initiation dose is below Dc, growth inertia breaks down, leading to substantial defect re-nucleation. A dimensionless kinetic descriptor, termed inertia potential Q, was derived from defect kinetics to quantify the underlying mechanisms. The generality of growth inertia was examined in both Mo-based alloys and pure Mo, with pure Mo exhibiting a lower Tc (∼300–400 °C), consistent with OKMC simulation predictions that Q decreases with increasing Re content. Furthermore, when a sufficient initiation dose (above Dc) is provided, high-temperature pre-irradiation suppresses subsequent nucleation at lower temperatures, yielding a sparse large-loop microstructure with reduced irradiation hardening. These findings establish defect initiation as a governing factor in irradiation evolution and provide a quantitative framework for predicting microstructural stability under variable-temperature irradiation conditions.
KW - Dislocation loop
KW - In-situ TEM
KW - Molybdenum-based alloy
KW - OKMC simulation
KW - Variable-temperature irradiation
UR - https://www.scopus.com/pages/publications/105035398655
U2 - 10.1016/j.jmst.2026.03.053
DO - 10.1016/j.jmst.2026.03.053
M3 - 文章
AN - SCOPUS:105035398655
SN - 1005-0302
VL - 274
SP - 266
EP - 277
JO - Journal of Materials Science and Technology
JF - Journal of Materials Science and Technology
ER -