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<p>Nuclear energy is pivotal for global decarbonization, yet severe accident mitigation—particularly core melt stabilization—remains a major safety challenge. Traditional cement-based sacrificial materials, reliant on Fe₂O₃/SiO₂ for melt oxidation, are hindered by high free-water content (posing hydrogen explosion risks) and inadequate high-temperature integrity. While existing research on barium ferrite (BF) incorporation has focused on conventional silicon-based systems, its effects in silicon-iron composite sacrificial matrices remain unexplored. This study fills this gap by developing a novel BF-incorporated ferro-silicon sacrificial mortar (FM). The key innovation lies in utilizing BF to concurrently achieve low free-water content (&lt; 5%) and self-compacting workability (slump flow: 240 ± 5&#xa0;mm) within this composite system, effectively mitigating hydrogen risk while ensuring castability. However, BF’s inert properties reduce mechanical performance: compressive strength declines from 59.9&#xa0;MPa to 46.09&#xa0;MPa, flexural strength drops by 13.03%, and porosity rises, worsening chloride resistance (62.2% higher ion migration). Microstructural analysis reveals BF-induced interfacial defects as the primary cause. High-temperature testing (1000&#xa0;°C) shows FM retains just 12.3–13.3% of its compressive strength, with polypropylene fiber preventing spalling by dissipating steam pressure. Despite pore structure degradation from C-S-H gel decomposition, the 10% BF formulation optimizes trade-offs-maintaining free water below 4.56%, compressive strength above 56.61&#xa0;MPa, and stable pore structures. The research underscores FM’s potential as a safer alternative for nuclear sacrificial materials, addressing critical gaps in melt stabilization technology. By quantifying FM’s dual role (safety enhancement vs. mechanical trade-offs), it offers actionable guidelines for material design, supporting both reactor safety and low-carbon energy goals.</p>

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Microstructure and performance of barium ferrite-modified sacrificial mortar for nuclear safety: mitigating hydrogen risk and enhancing high-temperature resistance

  • 期刊论文

  • 发表日期：

    2026年4月15日

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  • Xiaojing Song,
  • Hongyan Chu,
  • Jinyang Jiang,
  • Fengjuan Wang

摘要

Nuclear energy is pivotal for global decarbonization, yet severe accident mitigation—particularly core melt stabilization—remains a major safety challenge. Traditional cement-based sacrificial materials, reliant on Fe₂O₃/SiO₂ for melt oxidation, are hindered by high free-water content (posing hydrogen explosion risks) and inadequate high-temperature integrity. While existing research on barium ferrite (BF) incorporation has focused on conventional silicon-based systems, its effects in silicon-iron composite sacrificial matrices remain unexplored. This study fills this gap by developing a novel BF-incorporated ferro-silicon sacrificial mortar (FM). The key innovation lies in utilizing BF to concurrently achieve low free-water content (< 5%) and self-compacting workability (slump flow: 240 ± 5 mm) within this composite system, effectively mitigating hydrogen risk while ensuring castability. However, BF’s inert properties reduce mechanical performance: compressive strength declines from 59.9 MPa to 46.09 MPa, flexural strength drops by 13.03%, and porosity rises, worsening chloride resistance (62.2% higher ion migration). Microstructural analysis reveals BF-induced interfacial defects as the primary cause. High-temperature testing (1000 °C) shows FM retains just 12.3–13.3% of its compressive strength, with polypropylene fiber preventing spalling by dissipating steam pressure. Despite pore structure degradation from C-S-H gel decomposition, the 10% BF formulation optimizes trade-offs-maintaining free water below 4.56%, compressive strength above 56.61 MPa, and stable pore structures. The research underscores FM’s potential as a safer alternative for nuclear sacrificial materials, addressing critical gaps in melt stabilization technology. By quantifying FM’s dual role (safety enhancement vs. mechanical trade-offs), it offers actionable guidelines for material design, supporting both reactor safety and low-carbon energy goals.