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.