Please use this identifier to cite or link to this item: https://hdl.handle.net/20.500.14365/939
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dc.contributor.authorErenturk, Sema Akyil-
dc.contributor.authorBengisu, Murat-
dc.contributor.authorErdogan, Cem-
dc.date.accessioned2023-06-16T12:48:02Z-
dc.date.available2023-06-16T12:48:02Z-
dc.date.issued2017-
dc.identifier.issn0236-5731-
dc.identifier.issn1588-2780-
dc.identifier.urihttps://doi.org/10.1007/s10967-017-5536-z-
dc.identifier.urihttps://hdl.handle.net/20.500.14365/939-
dc.description.abstractProperties of sodium borate glasses, including chemical durability, leaching rate, glass transformation temperature, and melting temperature were analyzed for waste immobilization applications. The lowest dissolution rate (1.6 x 10(-8) g cm(-2) min(-1)) among candidate sodium borate host glasses was achieved in 45Na(2)O center dot 5P(2)O(5)center dot 5PbO center dot 45B(2)O(3). Similarly, the lowest dissolution rate (5.5 x 10(-8) g cm(-2) min(-1)) for simulated waste glass compositions was achieved in 20SrO center dot 80(30Na(2)O center dot 60PbO center dot 10B(2)O(3)). Clear vitrified waste products containing up to 35 mol% SrO and 25 mol% Cs2O were obtained. Low melting temperatures ranging from 222 to 440 A degrees C were achieved in simulated waste glasses.en_US
dc.description.sponsorshipTUBITAK funds [109M294]en_US
dc.description.sponsorshipThis work was supported by TUBITAK funds under project No. 109M294. We are thankful to Dr. S. Yusan and Z. Camtakan for their kind assistance during experimental studies.en_US
dc.language.isoenen_US
dc.publisherSpringeren_US
dc.relation.ispartofJournal of Radıoanalytıcal And Nuclear Chemıstryen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectBorate glassesen_US
dc.subjectRadioactive wasteen_US
dc.subjectVitrified wasteen_US
dc.subjectChemical durabilityen_US
dc.subjectStructural characterizationen_US
dc.subjectChemical Durabilityen_US
dc.subjectSilicate-Glassesen_US
dc.subjectPbo-B2o3 Glassesen_US
dc.subjectRemovalen_US
dc.titleEvaluation of Sodium Borate Glasses for Radioactive Waste Immobilization Applicationsen_US
dc.typeArticleen_US
dc.identifier.doi10.1007/s10967-017-5536-z-
dc.identifier.scopus2-s2.0-85031427231-
dc.departmentİzmir Ekonomi Üniversitesien_US
dc.authoridERENTURK, Sema/0000-0001-9938-1285-
dc.authoridBengisu, Murat/0000-0001-6814-5861-
dc.authorwosidERENTURK, Sema/O-1053-2013-
dc.authorwosidBengisu, Murat/AAY-3983-2020-
dc.authorscopusid56636642300-
dc.authorscopusid6603708300-
dc.authorscopusid55955285300-
dc.identifier.volume314en_US
dc.identifier.issue3en_US
dc.identifier.startpage2069en_US
dc.identifier.endpage2086en_US
dc.identifier.wosWOS:000416545300062-
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.identifier.scopusqualityQ3-
item.openairetypeArticle-
item.grantfulltextreserved-
item.languageiso639-1en-
item.cerifentitytypePublications-
item.openairecristypehttp://purl.org/coar/resource_type/c_18cf-
item.fulltextWith Fulltext-
crisitem.author.dept06.03. Industrial Design-
Appears in Collections:Scopus İndeksli Yayınlar Koleksiyonu / Scopus Indexed Publications Collection
WoS İndeksli Yayınlar Koleksiyonu / WoS Indexed Publications Collection
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