1996
DOI: 10.1007/bf02163562
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Leachability of cobalt and cesium from natural and chemically treated zeolites

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Cited by 8 publications
(3 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: 98%
“…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: 98%
“…(b) The addition of 10% of natural clays decrease the CLF for the studied radionuclides, and this can be attributed to the low porosity of these additives that can reduce the overall porosity of the waste matrix when compared with that of plain cement matrix and also to the high sorption capacity of those natural clays for the studied radionuclides [18][19][20]. (c) The CLF from OPC-bentonite waste matrix is lower than that from OPC-red clay and this may be related to the higher sorption capacity of bentonite, towards all the studied radionuclides, than red clay.…”
Section: Leaching Charachterisitcs Of 137 Cs 60 Co and 152154 Eu Rmentioning
confidence: 97%
“…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%