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This study was conducted to treat radioactive acidic wastewater, which contained radioactive 60Co and 152Eu. The wastewater can be generated during a decommissioning project to reduce the volume of radioactive concrete waste from nuclear facilities. With a variety of methods for separating the radioactive nuclides available, we evaluated the separation applicability of the solvent extraction method. From our results, Co and Eu could be easily extracted from the Ca rich wastewater using Cyanex301 (Co extraction (%) 99.8, Eu extraction (%) 99.6) without Ca extraction. On the other hand, Eu could be selectively separated by Cyanex272 (Eu extraction (%) 99.1) without Co and Ca extraction at pH 2~3. Therefore, the extraction method can be tailored according to the target radionuclides present in the wastewater and be selectively applied to the overall treatment process. By extracting radioactive Co and Eu from acidic wastewater to below the discharge criteria, treated wastewater could be regarded as non-radioactive industrial waste, to be economically and easily handled. Moreover, it may be possible to reuse separated Co and Eu for research and industrial applications by realizing waste valorization.
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Tom
Strony
123--126
Opis fizyczny
Bibliogr. 12 poz., rys., tab., wzory
Twórcy
autor
- Korea Atomic Energy Research Institute (KAERI), Decommissioning Technology Research Division, 111, Daedeok-Daero 989 Beon-Gil, Yuseong-Gu, Daejeon, 34057, Republic of Korea
- Yonsei University, Department of Chemical and Biomolecular Engineering, 50 Yonsei-ro, Seodaemun-gu, Seoul, 03722, Republic of Korea
autor
- Korea Atomic Energy Research Institute (KAERI), Decommissioning Technology Research Division, 111, Daedeok-Daero 989 Beon-Gil, Yuseong-Gu, Daejeon, 34057, Republic of Korea
autor
- Korea Atomic Energy Research Institute (KAERI), Decommissioning Technology Research Division, 111, Daedeok-Daero 989 Beon-Gil, Yuseong-Gu, Daejeon, 34057, Republic of Korea
- Seoul National University, Nuclear Research Institute for Future Technology and Policy, 1 Gwanak-ro, Gwanak-gu, Seoul 08826, Republic of Korea
autor
- Korea Atomic Energy Research Institute (KAERI), Decommissioning Technology Research Division, 111, Daedeok-Daero 989 Beon-Gil, Yuseong-Gu, Daejeon, 34057, Republic of Korea
autor
- Yonsei University, Department of Chemical and Biomolecular Engineering, 50 Yonsei-ro, Seodaemun-gu, Seoul, 03722, Republic of Korea
Bibliografia
- [1] International Atomic Energy Agency, Managing Low Radioactivity Material from the Decommissioning of Nuclear Facilities, Vienna 2008.
- [2] International Atomic Energy Agency, Application of the Concepts of Exclusion, Exemption and Clearance, Vienna 2004.
- [3] M. Oh, K. Lee, R.I. Foster, C.H. Lee, J. Environ. Chem. Eng. 9 (4), 105742 (2021).
- [4] International Atomic Energy Agency, Setting Authorized Limits for Radioactive Discharges: Practical Issues to Consider, Vienna 2010.
- [5] T. Goto, M. Smutz, J. Inorg. and Nucl. Chem. 27 (6), 1369-1379 (1965).
- [6] J. Rydberg, Solvent Extraction Principles and Practice Revised and Expanded (2nd ed.), CRC Press 2004.
- [7] K. Omelchuk, P. Szczepański, A. Shrotre, M. Haddad, A. Chagnes, RSC Adv. 7, 5660 (2017).
- [8] D. Peppard, W. Driscoll, R. Sirobien, S. Mccarty, J. Inorg. Nuel. Chem. 4, 326-333 (1957).
- [9] H.S. Moon, S.J. Song, T.T. Tran, M. Lee, Resources Recycling 29 (5), 55-63 (2020).
- [10] V.N.H. Nguyen, T.H. Nguyen, M. Lee, Metals 10 (8), 1105 (2020).
- [11] K.C. Sole, J.B. Hiskey, Hydrometallurgy 37, 129-147(1995).
- [12] C. Bourget, B. Jakovljevic, D. Nucciarone, Hydrometallurgy 77 (3-4), 203-218 (2005).
Uwagi
1. This work was supported by the National Research Foundation of Korea grant (No. RS-2022-00155421) funded by the Ministry of Science and ICT.
2. Opracowanie rekordu ze środków MEiN, umowa nr SONP/SP/546092/2022 w ramach programu "Społeczna odpowiedzialność nauki" - moduł: Popularyzacja nauki i promocja sportu (2022-2023).
Typ dokumentu
Bibliografia
Identyfikator YADDA
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