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http://dx.doi.org/10.1016/j.net.2020.12.017

Radiological safety evaluation of dismantled radioactive concrete from Kori Unit 1 in the disposal and recycling process  

Lee, ChoongWie (Ulsan National Institute of Science and Technology)
Kim, Hee Reyoung (Ulsan National Institute of Science and Technology)
Lee, Seung Jun (Ulsan National Institute of Science and Technology)
Publication Information
Nuclear Engineering and Technology / v.53, no.6, 2021 , pp. 2019-2024 More about this Journal
Abstract
For evaluating the radiological safety of dismantled concrete, the process of disposal and recycling of the radioactive concrete generated during the dismantling of Kori Unit 1 is analyzed. Four scenarios are derived based on the analysis of the concrete recycling and disposal process, and the potential exposure to the workers and public during this process are calculated. VISIPLAN and RESRAD code are used for evaluating the dosages received by the workers and public in the following four scenarios: concrete inspection, transport of concrete by the truck driver, driving on a recycled concrete road, and public living near the landfilled concrete waste. Two worker exposure scenarios in the processing of concrete and two public exposure scenarios in recycling and disposal are considered; in all the scenarios, the exposure dose does not exceed the annual dose limit for each representative.
Keywords
Concrete; Processing; Decommissioning; Dose assessment; Disposal;
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