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<p>In this paper, FeCrAl alloys strengthened via dispersed ZrC particles were fabricated by mechanical alloying (MA) and spark plasma sintering (SPS) techniques. The influences of sintering temperature and nano-scale ZrC addition on the microstructure and mechanical properties of the FeCrAl alloys were investigated. The 05ZrC-FeCrAl alloy sintered at 1000&#xa0;°C exhibited a maximum tensile strength of 1058&#xa0;MPa and a hardness of 318.2&#xa0;HV, which were closely associated with the grain structure and ZrC distribution. Compared to the pure FeCrAl alloy, the 05ZrC-FeCrAl alloy displayed finer grain size and more dispersed ZrC particles, confirming that the addition of ZrC could effectively suppress the grain boundary migration and dislocation recovery behaviors. As a result, the introduction of ZrC could simultaneously reinforce the grain boundary strengthening, dispersion strengthening and dislocation strengthening effects in the FeCrAl alloys. The alloying strategy developed in this work provides a novel pathway for designing advanced structural materials for nuclear reactors.</p>

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Microstructure and Mechanical Properties of FeCrAl Alloys Strengthened by Dispersed ZrC Particles

  • 期刊论文

  • 发表日期：

    2025年11月5日

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  • Yanzhen Liu,
  • Jingwen Zhang,
  • Liming Yu,
  • Tianyu Du,
  • Qiuzhi Gao,
  • Chenxi Liu,
  • Yongchang Liu,
  • Yuehua Liu

摘要

In this paper, FeCrAl alloys strengthened via dispersed ZrC particles were fabricated by mechanical alloying (MA) and spark plasma sintering (SPS) techniques. The influences of sintering temperature and nano-scale ZrC addition on the microstructure and mechanical properties of the FeCrAl alloys were investigated. The 05ZrC-FeCrAl alloy sintered at 1000 °C exhibited a maximum tensile strength of 1058 MPa and a hardness of 318.2 HV, which were closely associated with the grain structure and ZrC distribution. Compared to the pure FeCrAl alloy, the 05ZrC-FeCrAl alloy displayed finer grain size and more dispersed ZrC particles, confirming that the addition of ZrC could effectively suppress the grain boundary migration and dislocation recovery behaviors. As a result, the introduction of ZrC could simultaneously reinforce the grain boundary strengthening, dispersion strengthening and dislocation strengthening effects in the FeCrAl alloys. The alloying strategy developed in this work provides a novel pathway for designing advanced structural materials for nuclear reactors.