Byun H, Kim J, Yoon TB, Park JW. DEVELOPMENT OF SAFETY ASSESSMENT CODE FOR DECOMMISSIONING WASTE RECYCLING AND DISPOSAL.
Radiat Prot Dosimetry 2023;
199:ncac246-208. [PMID:
36521799 DOI:
10.1093/rpd/ncac246]
[Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Received: 05/02/2022] [Revised: 09/08/2022] [Accepted: 11/03/2022] [Indexed: 06/17/2023]
Abstract
In Korea, 10 units of nuclear power plants are projected for decommissioning by 2030, which will consequently generate a large amount of decommissioning waste. It could bring about a lack in the capacity of the radioactive waste disposal facility. In this paper, a computational code, REcycling and DIsposal Safety Assessment has been developed for the safety assessment regarding the recycling and disposal of the decommissioning waste. It is composed of two modules: dose assessment module and maximum allowance concentration estimation module. The dose assessment module is intended to evaluate the exposure doses from radioactive nuclides in the wastes for each recycling or disposal scenario. The maximum allowance concentration estimation module has the function to translate the nuclides concentrations in the wastes from the exposure doses received by the end user for each scenario. The concentration of each nuclide provides the basis for the development of the technical criteria in accordance with the annual dose limit.
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