废放射源近地表处置活度限值推导

以我国低中放固体废物北龙处置场和西北处置场为参考场址，针对钻探景象和钻探后景象，考虑了几个重要放射性核素，推导了废放射源在两个场址中处置的活度限值。除¹³⁷Cs的关键景象为钻探景象外，其他所选核素的关键景象均为钻探后景象。且单个废物包中的废放射源活度限值不受处置场的限制，推荐了适合于近地表处置的单个废物包内废放射源的接收限值，⁹⁰Sr、¹³⁷Cs、²³⁸Pu、^63Ni、²⁴¹Am、²²⁶Ra和²³⁹Pu分别为2.0×10¹⁰、6.0×10⁹、1.0×10⁶、1.0×10¹¹、1.0×10⁷、1.0×10⁶和8.0×10⁶Bq。

Derivation of Activity Limits of Spent Radioactive Source for Near Surface Disposal

Taking Beilong LILW reposititory and Northwestern China LILW reposititory as the reference sites, based on the drilling scenario and after drilling scenario, and considering some significant radionuclides, the activity limits for disposal of spent radioactive source in both sites were derived. The critical scenario for ¹³⁷Cs is drilling scenario, and after drilling scenario is the critical scenario for other radionuclides. The activity limits of spent radioactive source in one waste package are not restricted by the disposal site. The acceptance limits of spent radioactive source in one waste package are recommended, and the values for ⁹⁰Sr, ¹³⁷Cs, ²³⁸Pu, ⁶³Ni, ²⁴¹Am, ²²⁶Ra and ²³⁹Pu are 2.0×10¹⁰, 6.0×10⁹, 1.0×10⁶, 1.0×10¹¹, 1.0×10⁷, 1.0×10⁶ and 8.0×10⁶Bq, respectively.