2006
DOI: 10.1016/j.jhazmat.2005.12.020
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Immobilization of cesium and strontium radionuclides in zeolite-cement blends

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Cited by 160 publications
(51 citation statements)
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“…The cationic radioisotopes, present in the liquid effluents of low and intermediate level liquid wastes, can be removed by the ion exchange with the Na + ions of the zeolites. These inorganic materials possess high exchange capacity, possible selectivity and specificity, good resistant to radiation, and have proven advantages with respect to immobilization and final disposal when compared with organic ion exchangers [25][26][27][28][29][30][31][32]. This study is an extension of our previous work [13], where synthetic zeolite A material was chemically prepared, completely characterized and preliminary tested as an inorganic ion exchange material for application in radioactive waste treatment.…”
Section: Introductionmentioning
confidence: 99%
“…The cationic radioisotopes, present in the liquid effluents of low and intermediate level liquid wastes, can be removed by the ion exchange with the Na + ions of the zeolites. These inorganic materials possess high exchange capacity, possible selectivity and specificity, good resistant to radiation, and have proven advantages with respect to immobilization and final disposal when compared with organic ion exchangers [25][26][27][28][29][30][31][32]. This study is an extension of our previous work [13], where synthetic zeolite A material was chemically prepared, completely characterized and preliminary tested as an inorganic ion exchange material for application in radioactive waste treatment.…”
Section: Introductionmentioning
confidence: 99%
“…The specific conditioning of this element should optimize the global management of the package of high-level waste. Current Portland cement-based technologies for the concentration and immobilization of 135 Cs and 137 Cs are mainly used for low-level wastes, but often present unsatisfactory leaching behaviour [1], albeit several additives have been proposed to improve their leaching behaviour [2][3][4]. The borosilicate glass is the most common industrial solution used for the immobilization of high-level waste [5,6].…”
Section: Introductionmentioning
confidence: 99%
“…Polyethylene cylindrical shape moulds with internal height/diameter ratio of 1.0 (3.0 cm diameter and height) was used to prepare cement pastes [13,21,26]. Paste was placed in the moulds in two approximately equal layers.…”
Section: Moulding and Curingmentioning
confidence: 99%
“…Recently, an extensive array of leaching studies has been addressed to reduce the leachability of different radionuclides from immobilized waste matrices by mixing the cement with different materials having significant sorption capacity such as fly ash, silica fume, ilmenite, blast furnace slag, kaolin, and zeolites [10][11][12][13][14][15][16][17][18][19][20][21][22]. These additives were utilized either to enhance the compressive strength of the grout mixture or increase its resistibility to leaching.…”
Section: Introductionmentioning
confidence: 99%