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目的判断辐照装置退役60Co残留量是否满足《电离辐射防护与辐射源安全基本标准》(GB 18871-2002)104Bq/kg的豁免浓度与105Bq总活度的要求。方法采用高纯锗谱仪γ能谱分析方法进行60Co核素比活度分析,并根据放射性废物的总量进行60Co残留量估算。结果辐照室瓷砖60Co残余量74 665 Bq,水泥60Co残余量84 420 Bq,蒸发池底泥60Co残余量7458 Bq,泵房渣土791 Bq,总残余量92 669 Bq,平均比活度为226.3 Bq/kg。结论辐照装置60Co残留量满足《电离辐射防护与辐射源安全基本标准》(GB18871-2002)104Bq/kg的豁免浓度与105Bq总活度要求。
Objective To determine if 60Co residues in decommissioned irradiated units meet the requirements of the exemption concentration of 104Bq / kg and the total activity of 105Bq in the “Basic Standard for Safety of Ionizing Radiation Protection and Radiation Sources” (GB 18871-2002). Methods The 60Co nuclide specific activity was analyzed by γ-ray spectrometry with high-purity germanium spectrometer and the 60Co residue was estimated based on the total amount of radioactive waste. Results The residual volume of 60Co in the irradiation chamber was 74 665 Bq, the residual amount of 60Co in the cement was 84 420 Bq, the residual amount of 60Co in the bottom of the evaporation pond was 7458 Bq, the residual amount of pump room was 791 Bq, and the total residual capacity was 92 669 Bq. The average specific activity was 226.3 Bq / kg. Conclusion The residual 60Co of the irradiation device meets the requirement of 104Bq / kg exemption concentration and 105Bq total activity requirement of “Basic Standard for Protection against Ionizing Radiation and Safety of Radiation Sources” (GB18871-2002).