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<p>This study, adhering to the Chinese standard GB/T 34008-2017, introduces a penalty-function-based particle swarm optimization algorithm and proposes an innovative approach for optimizing the aggregate mix ratio in radiation-shielding concrete. Utilizing barite, magnetite, and hematite as aggregates, the proposed optimization method yielded optimal mix ratios tailored for shielding 4.5 and 10 MeV neutrons while achieving target compressive strengths of 35 and 40 MPa. Geant4 simulations and experimental validations confirm that the optimized concrete offers robust neutron and gamma-ray shielding properties. Compared to conventional concrete, it achieves a 20.89% reduction in maximum neutron absorption dose and enhances the gamma-ray linear attenuation coefficient by up to 43.17%. The developed optimization method offers valuable guidance for shielding design in nuclear technology application laboratories.</p>

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Optimized mix proportion design for radiation-shielding concrete using particle swarm optimization: a case study on fast neutron and gamma shielding

  • 期刊论文

  • 发表日期：

    2025年2月21日

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  • Haoxuan Li,
  • Fengdi Qin,
  • Zhongkai Fan,
  • Hui Yang,
  • Tianyu Deng,
  • Xiangming Cai,
  • Xuwei Zeng,
  • Hongliang Li,
  • Jian Shan

摘要

This study, adhering to the Chinese standard GB/T 34008-2017, introduces a penalty-function-based particle swarm optimization algorithm and proposes an innovative approach for optimizing the aggregate mix ratio in radiation-shielding concrete. Utilizing barite, magnetite, and hematite as aggregates, the proposed optimization method yielded optimal mix ratios tailored for shielding 4.5 and 10 MeV neutrons while achieving target compressive strengths of 35 and 40 MPa. Geant4 simulations and experimental validations confirm that the optimized concrete offers robust neutron and gamma-ray shielding properties. Compared to conventional concrete, it achieves a 20.89% reduction in maximum neutron absorption dose and enhances the gamma-ray linear attenuation coefficient by up to 43.17%. The developed optimization method offers valuable guidance for shielding design in nuclear technology application laboratories.