Mathematical modelling of immobilization of radionuclides Cs-137 and Co-60 in concrete matrix
Apstrakt
Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using an empirical method employing a polynomial equation. To assess the safety for disposal of radioactive waste-cement composition, the leaching of Cs-137 and Co-60, from a waste composite into a surrounding fluid has been studied. Leaching tests were carried out in accordance with a method recommended by IAEA. Determination of retardation factors, K-F and coefficients of distribution, k(d), using a simplified mathematical model for analyzing the migration of radionuclides, have been developed. Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using an empirical method employing a polynomial equation. In our experiment we have analized mechanism of Cs-137 and Co-60 leaching values during a period of 60 days. Results presented in this paper are examples of results obtained in a 25-year mortar and con...crete testing project, which will influence the design of the engineered trenches system for a future central Serbian radioactive waste storage center. (C) 2010 Elsevier Ltd. All rights reserved.
Ključne reči:
Leaching / Retardation factor / Immobilization / Radioactive wasteIzvor:
Progress in Nuclear Energy, 2010, 52, 7, 685-688
DOI: 10.1016/j.pnucene.2010.03.005
ISSN: 0149-1970
WoS: 000279441400012
Scopus: 2-s2.0-77953229443
Kolekcije
Institucija/grupa
VinčaTY - JOUR AU - Plećaš, Ilija B. PY - 2010 UR - https://vinar.vin.bg.ac.rs/handle/123456789/4029 AB - Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using an empirical method employing a polynomial equation. To assess the safety for disposal of radioactive waste-cement composition, the leaching of Cs-137 and Co-60, from a waste composite into a surrounding fluid has been studied. Leaching tests were carried out in accordance with a method recommended by IAEA. Determination of retardation factors, K-F and coefficients of distribution, k(d), using a simplified mathematical model for analyzing the migration of radionuclides, have been developed. Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using an empirical method employing a polynomial equation. In our experiment we have analized mechanism of Cs-137 and Co-60 leaching values during a period of 60 days. Results presented in this paper are examples of results obtained in a 25-year mortar and concrete testing project, which will influence the design of the engineered trenches system for a future central Serbian radioactive waste storage center. (C) 2010 Elsevier Ltd. All rights reserved. T2 - Progress in Nuclear Energy T1 - Mathematical modelling of immobilization of radionuclides Cs-137 and Co-60 in concrete matrix VL - 52 IS - 7 SP - 685 EP - 688 DO - 10.1016/j.pnucene.2010.03.005 ER -
@article{ author = "Plećaš, Ilija B.", year = "2010", abstract = "Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using an empirical method employing a polynomial equation. To assess the safety for disposal of radioactive waste-cement composition, the leaching of Cs-137 and Co-60, from a waste composite into a surrounding fluid has been studied. Leaching tests were carried out in accordance with a method recommended by IAEA. Determination of retardation factors, K-F and coefficients of distribution, k(d), using a simplified mathematical model for analyzing the migration of radionuclides, have been developed. Transport phenomena involved in the leaching of a radioactive material from a cement composite matrix are investigated using an empirical method employing a polynomial equation. In our experiment we have analized mechanism of Cs-137 and Co-60 leaching values during a period of 60 days. Results presented in this paper are examples of results obtained in a 25-year mortar and concrete testing project, which will influence the design of the engineered trenches system for a future central Serbian radioactive waste storage center. (C) 2010 Elsevier Ltd. All rights reserved.", journal = "Progress in Nuclear Energy", title = "Mathematical modelling of immobilization of radionuclides Cs-137 and Co-60 in concrete matrix", volume = "52", number = "7", pages = "685-688", doi = "10.1016/j.pnucene.2010.03.005" }
Plećaš, I. B.. (2010). Mathematical modelling of immobilization of radionuclides Cs-137 and Co-60 in concrete matrix. in Progress in Nuclear Energy, 52(7), 685-688. https://doi.org/10.1016/j.pnucene.2010.03.005
Plećaš IB. Mathematical modelling of immobilization of radionuclides Cs-137 and Co-60 in concrete matrix. in Progress in Nuclear Energy. 2010;52(7):685-688. doi:10.1016/j.pnucene.2010.03.005 .
Plećaš, Ilija B., "Mathematical modelling of immobilization of radionuclides Cs-137 and Co-60 in concrete matrix" in Progress in Nuclear Energy, 52, no. 7 (2010):685-688, https://doi.org/10.1016/j.pnucene.2010.03.005 . .