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Determining the Optimal Conditions for the Sample Quantity of Radioactive Sludge

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
초록

Typically, the bottom of the effluent treatment facility at a nuclear power plant contains sediment, which is low-contamination waste consisting of sludge, gravel, sand, and other materials from which radioactive contaminants have been removed. Among these sediments, sludge is an irregular solid form consisting of small particles that are coagulated together, with radioactive isotopes containing cobalt attached. Currently, there is a record of disposing of dry active waste from domestic nuclear power plants, and efforts are underway to gather basic data for the disposal of untreated waste such as sludge, spent filter, and spent resin. In particular, the classification and disposal methods of waste will be determined based on the radioactivity concentration. Therefore, plans are being made to determine the radioactivity concentration of radioactive isotopes and establish disposal plans for sludge samples. In this study, pre-treatment and solutionization were carried out for the analysis of radioactive isotopes in sludge sampels from nuclear power plants. The deviation of the gamma radioisotope analysis results was derived to obtain an optimal sample quantity that represents the sludge.

저자
  • Kahee Jeong(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI)) Corresponding author
  • Sooyeon Lim(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
  • Ji-Eun Park(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))
  • Wook Sohn(Korea Hydro and Nuclear Power (KHNP) Central Research Institute (KHNP-CRI))