• Nuclear Engineering and Technology
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• v.56 no.10
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• pp.4384-4389
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• 2024

NORM is used as a raw material in various industries worldwide. According to the IAEA, radiological effects may occur in the environment due to raw materials and by-products generated from NORM industries. The objective of this study was to assess radiological environmental impact of the phosphate processing industry to identify the radiological effects on the general public. The resident farmer scenario was chosen as the exposure scenario due to the living characteristics of the public around the facility and the conservatism of the assessment. The RESRAD-OFFSITE code was used to evaluate the radiation dose to the public. The maximum radiation dose to the public was 6.13 × 10^-3 mSv/y. Main exposure pathways were aquatic food ingestion, radon inhalation, and meat ingestion. The uranium series accounted for about 99 % of the total radiation dose, while the thorium series and K-40 nuclides accounted for less than 1 %. These study results can be used for management of radiological impact to the public around domestic NORM industries.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.19 no.1
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• pp.113-121
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• 2021

A safety assessment of radioactive waste repositories is a mandatory requirement process because there are possible radiological hazards owing to radionuclide migration from radioactive waste to the biosphere. For a reliable safety assessment, it is important to establish a parameter database that reflects the site-specific characteristics of the disposal facility and repository site. From this perspective, solubility, a major geochemical parameter, has been chosen as an important parameter for modeling the migration behavior of radionuclides. The solubilities were derived for Am, Ni, Tc, and U, which were major radionuclides in this study, and on-site groundwater data reflecting the operational conditions of the Gyeongju low and intermediate level radioactive waste (LILW) repository were applied to reflect the site-specific characteristics. The radiation dose was derived by applying the solubility and radionuclide inventory data to the RESRAD-OFFSITE code, and sensitivity analysis of the dose according to the solubility variation was performed. As a result, owing to the low amount of radionuclide inventory, the dose variation was insignificant. The derived solubility can be used as the main input data for the safety assessment of the Gyeongju LILW repository in the future.