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Leaching behavior of Co-60 and (CS)-C-137 from spent ion exchange resins in cement-bentonite clay matrix
dc.creator | Plećaš, Ilija B. | |
dc.creator | Pavlović, R | |
dc.creator | Pavlović, S | |
dc.date.accessioned | 2018-03-01T19:27:28Z | |
dc.date.available | 2018-03-01T19:27:28Z | |
dc.date.issued | 2004 | |
dc.identifier.issn | 0022-3115 | |
dc.identifier.uri | https://vinar.vin.bg.ac.rs/handle/123456789/2763 | |
dc.description.abstract | The leach rate of Co-60 and Cs-137 from two different ion exchange resins: (a) spent cation exchange resins and (b) spent mix bead ion exchange resins in cement-bentonite matrix has been studied. The solidification matrix was a standard Portland cement mixed with 290-350 kg/m(3) spent cation exchange resins, with or without 2-5% of bentonite clay. The leach rates from the cement-bentonite matrix as Co-60: (4.2-7.3) x 10(-5) cm/d, and for Cs-137: (3.2-6.6) x 10-5 cm/d, after 245 days were measured. From the leaching data the apparent diffusivity of cobalt and cesium in cement-bentonite clay matrix with a waste load of 290-350 kg/m(3) spent cation exchange resins was measured as Co-60: (1.0-4.0) x 10(-6) cm(2)/d and for Cs-137: (0.5-2.6) x 10(-4) cm(2)/d after 245 days. These results are part of a 20-year mortar and concrete testing project which will influence the design of radioactive waste management for a future Serbian radioactive waste disposal center. (C) 2004 Elsevier B.V. All rights reserved. | en |
dc.rights | restrictedAccess | en |
dc.source | Journal of Nuclear Materials | en |
dc.title | Leaching behavior of Co-60 and (CS)-C-137 from spent ion exchange resins in cement-bentonite clay matrix | en |
dc.type | article | en |
dcterms.abstract | Плецас, И; Павловиц, Р; Павловиц, С; | |
dc.citation.volume | 327 | |
dc.citation.issue | 2-3 | |
dc.citation.spage | 171 | |
dc.citation.epage | 174 | |
dc.identifier.wos | 000220936900011 | |
dc.identifier.doi | 10.1016/j.jnucmat.2004.02.001 | |
dc.citation.rank | M21a | |
dc.identifier.scopus | 2-s2.0-1842484257 |
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