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Growth inertia of irradiation defects and its governing role in microstructural evolution in Mo-Re alloys

  • Dewang Cui
  • , Tian Ren Yang
  • , Ziqi Cao
  • , Jingjing Liao
  • , Xi Qiu
  • , Yiwei Wang
  • , Wei Zhang
  • , Yuanming Li
  • , Xun Dai
  • , Quan Li
  • , Chao Sun
  • , Chengen Li
  • , Yu Hao Li
  • , Hong Bo Zhou*
  • , Guang Ran
  • *Corresponding author for this work
  • Xiamen University
  • Fujian Research Center for Nuclear Engineering
  • Beihang University
  • Nuclear Power Institute of China

Research output: Contribution to journalArticlepeer-review

Abstract

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.

Original languageEnglish
Pages (from-to)266-277
Number of pages12
JournalJournal of Materials Science and Technology
Volume274
DOIs
StatePublished - 10 Dec 2026

Keywords

  • Dislocation loop
  • In-situ TEM
  • Molybdenum-based alloy
  • OKMC simulation
  • Variable-temperature irradiation

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