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<p>Zirconium hydride is&#xa0;a commonly used neutron moderator material in compact nuclear reactors; however, its cracking behavior under irradiation conditions remains inadequately characterized. In this work, the irradiation-induced cracking behavior of zirconium hydride was systematically investigated through a combination of SRIM-based damage simulations and controlled deuterium ion irradiation experiments. The results demonstrate a pronounced dose-dependent increase in cumulative crack length over the irradiation damage range (0.16–31.27 dpa). At low doses (0.16–2.02 dpa), both the number and total length of cracks increase significantly, primarily due to grain coarsening, crack nucleation, and accelerated crack propagation. In contrast, at higher doses (18.94–31.27 dpa), the number of cracks tends to saturate and the increase in crack length slows down, indicating that crack propagation mainly occurs through the slow growth of existing crack structures. This work reveals the irradiation-induced cracking mechanism in zirconium hydride and provide critical support for its safe application in advanced reactor environments.</p>

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Mechanistic study on ion irradiation-induced cracking behavior of zirconium hydride

  • 期刊论文

  • 发表日期：

    2026年3月2日

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  • Xingyu Jiang,
  • Jiansong Zhang,
  • Huaping Mei,
  • Taosheng Li,
  • Feifei Song,
  • Yongju Sun,
  • Chao Chen

摘要

Zirconium hydride is a commonly used neutron moderator material in compact nuclear reactors; however, its cracking behavior under irradiation conditions remains inadequately characterized. In this work, the irradiation-induced cracking behavior of zirconium hydride was systematically investigated through a combination of SRIM-based damage simulations and controlled deuterium ion irradiation experiments. The results demonstrate a pronounced dose-dependent increase in cumulative crack length over the irradiation damage range (0.16–31.27 dpa). At low doses (0.16–2.02 dpa), both the number and total length of cracks increase significantly, primarily due to grain coarsening, crack nucleation, and accelerated crack propagation. In contrast, at higher doses (18.94–31.27 dpa), the number of cracks tends to saturate and the increase in crack length slows down, indicating that crack propagation mainly occurs through the slow growth of existing crack structures. This work reveals the irradiation-induced cracking mechanism in zirconium hydride and provide critical support for its safe application in advanced reactor environments.