乏燃料深钻孔处置安全试评价

Preliminary safety assessment of deep borehole disposal for spent fuel(SF)

为探讨乏燃料深钻孔处置方式的安全性,本文在已有处置概念设计基础上,以某乏燃料核素类型与活度作为输入源项,通过保守假设选取处置孔上方打井饮水景象开展安全评价计算,得出所致最大个人有效剂量为0.045 mSv/a,最大剂量出现在处置孔关闭后的8200年,主要剂量贡献核素为I-129,该结果可为我国高放废物深钻孔处置的研发提供参考。

In this article,a preliminary safety assessment calculation is taken to discuss the safety of deep borehole disposal of SF.The calculation work is based on existing conceptual design with input source term chosen from a specific SF’s radionuclides.For the radionuclide migration pathway,drinking water though well above the disposal borehole is selected under conservative assumption.Calculation result shows that the maximum individual radiation dose is 0.045 mSv/a,arising in the 8200 year after closure of the disposal borehole,which was mainly caused by I-129.This result can provide a good reference for R&D work of deep borehole disposal in China.