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During the period when the higher dose rate waste bucket/drum is loaded into the shielded container, the waste bucket/drum without top shielding will cause scattering inside and outside the plant and increase the radiation risk to personnel. The Monte Carlo method is used to simulate the typical scattering scene of a nuclear power plant (NPP) in this paper. A fast method to judge whether the scattering effect can be ignored based on the wall thickness of the shielded container is proposed. Based on the dose rate measurement data of the special topic of scattering impact transformation of a NPP, the results show that the theoretical analysis results are consistent with the actual measurement data. The quantitative evaluation results based on the calculation of the typical waste bucket/drum size of the NPP can provide theoretical support for the design of shielded containers of NPPs and the optimization of radiation protection during waste transfer.

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γ-Scattering Evaluation of the Impact of Internal and External of the Building Under the Scene of Lack of Top Shielding in Radioactive Waste Buckets of NPP

  • 会议论文

  • 发表日期：

    2026年

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  • Zhenyu Jiang,
  • Yonghai Zhou,
  • Jie Liu,
  • Yujia Chen

摘要

During the period when the higher dose rate waste bucket/drum is loaded into the shielded container, the waste bucket/drum without top shielding will cause scattering inside and outside the plant and increase the radiation risk to personnel. The Monte Carlo method is used to simulate the typical scattering scene of a nuclear power plant (NPP) in this paper. A fast method to judge whether the scattering effect can be ignored based on the wall thickness of the shielded container is proposed. Based on the dose rate measurement data of the special topic of scattering impact transformation of a NPP, the results show that the theoretical analysis results are consistent with the actual measurement data. The quantitative evaluation results based on the calculation of the typical waste bucket/drum size of the NPP can provide theoretical support for the design of shielded containers of NPPs and the optimization of radiation protection during waste transfer.