Radiological assessment on spent resin treatment facility and transportation for radioactive waste disposal

Abstract

Several radionuclides including tritium generated in heavy-water reactor nuclear power plants are managed through ion-exchange resins, and these spent resins are then stored in storage tanks. To maintain the capacity of the storage tanks, the waste sludge should be treated using appropriate methods. Dose assessments are conducted to ensure radiological safety during the treatment and disposal of the spent resin. In this study, it is performed that a radiological evaluation of the operation of spent-resin waste treatment facilities and transportation of the radioactive waste—in a polymer concrete high-integrity container (PC-HIC) for spent resin disposal—of Wolseong Nuclear Power Plant, a heavy-water reactor nuclear power plant in Korea. Radiation workers using the spent resin treatment equipment, as well as radiation workers transporting PC-HIC to the disposal site and public spaces in the transportation route, were considered in the evaluation. The maximum dose received by radiation workers was 11.2 mSv, which is below the annual average dose limit of 20 mSv/year. Doses were below the limit at all routes, objects, and sampling locations. For waste truck drivers, the individual dose was 6.10E-03 mSv, which is also below the driver dose limit of 6 mSv. The treatment and disposal of the spent resin operations are performed while maintaining the individual doses below the dose limits set for the practices.