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Efficient Radiochemical Analysis of Carbon-14 in Radioactive Wastes

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

Disposal of radioactive waste requires radiological characterization. Carbon-14 (C-14) is a volatile radionuclide with a long half-life, and it is one of the important radionuclides in a radioactive waste management. For the accurate liquid scintillation counter (LSC) analysis of a pure beta-emitting C-14, it should be separated from other beta emitters after extracted from the radioactive wastes since the LSC spectrum signals from C-14 overlaps with those from other beta-emitting nuclides in the extracted solutions. There have been three representative separation methods for the analysis of volatile C-14 such as acid digestion, wet oxidation, and pyrolysis. Each method has its own pros and cons. For example, the acid digestion method is easily accessible, but it involves the use of strong acids and generates large amount of secondary wastes. Moreover, it requires additional time-consuming purification steps and the skillful operators. In this study, more efficient and environment-friendly C-14 analysis method was suggested by adopting the photochemical reactions via in-situ decomposition using UV light source. As an initial step for the demonstration of the feasibility of the proposed method, instead of using radioactive C-14 standards, non-radioactive inorganic and organic standards were investigated to evaluate the recovery of carbon as a preliminary study. These standards were oxidized with chemical oxidants such as H2O2 or K2S2O8 under UV irradiations, and the generated CO2 was collected in Carbo-Sorb E solution. Recovery yield of carbon was measured based on the gravimetric method. As an advanced oxidation process, our photocatalytic oxidation will be promising as a time-saving method with less secondary wastes for the quantitative C-14 analysis in low-level radioactive wastes.

저자
  • Eunkyeom Lee(University of Science and Technology (UST), Korea Atomic Energy Research Institute (KAERI))
  • Chan-Yong Jung(Korea Atomic Energy Research Institute (KAERI))
  • Junhyuck Kim(Korea Atomic Energy Research Institute (KAERI))
  • Tae-Hyeong Kim(Korea Atomic Energy Research Institute (KAERI))
  • Jeongmook Lee(University of Science and Technology (UST), Korea Atomic Energy Research Institute (KAERI))
  • DongWoo Lee(Korea Atomic Energy Research Institute (KAERI))
  • Byungman Kang(Korea Atomic Energy Research Institute (KAERI))
  • Jong-Yun Kim(University of Science and Technology (UST), Korea Atomic Energy Research Institute (KAERI)) Corresponding author