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Evaluation of Americium Solubility in Synthesized Groundwater: Geochemical Modeling and Experimental Study at Over-Saturation Conditions

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영문명
발행기관
한국방사성폐기물학회
저자명
Hee-Kyung Kim Hye-Ryun Cho
간행물 정보
『Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT)』Vol.20 No.4, 399~410쪽, 전체 12쪽
주제분류
공학 > 공학일반
파일형태
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발행일자
2022.12.30
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The solubility and species distribution of radionuclides in groundwater are essential data for the safety assessment of deep underground spent nuclear fuel (SNF) disposal systems. Americium is a major radionuclide responsible for the long-term radiotoxicity of SNF. In this study, the solubility of americium compounds was evaluated in synthetic groundwater (Syn-DB3), simulating groundwater from the DB3 site of the KAERI Underground Research Tunnel. Geochemical modeling was performed using the ThermoChimie_11a thermochemical database. Concentration of dissolved Am(III) in Syn-DB3 in the pH range of 6.4–10.5 was experimentally measured under over-saturation conditions by liquid scintillation counting over 70 d. The absorption spectra recorded for the same period suggest that Am(III) colloidal particles formed initially followed by rapid precipitation within 2 d. In the pH range of 7.5–10.5, the concentration of dissolved Am(III) converged to approximately 2×10−7 M over 70 d, which is comparable to that of the amorphous AmCO3OH(am) according to the modeling results. As the samples were aged for 70 d, a slow equilibrium process occurred between the solid and solution phases. There was no indication of transformation of the amorphous phase into the crystalline phase during the observation period.

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APA

Hee-Kyung Kim,Hye-Ryun Cho. (2022).Evaluation of Americium Solubility in Synthesized Groundwater: Geochemical Modeling and Experimental Study at Over-Saturation Conditions. Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT), 20 (4), 399-410

MLA

Hee-Kyung Kim,Hye-Ryun Cho. "Evaluation of Americium Solubility in Synthesized Groundwater: Geochemical Modeling and Experimental Study at Over-Saturation Conditions." Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT), 20.4(2022): 399-410

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