Chemical Durability and Structural Analysis of Pbo-B2o3 Glasses and Testing for Simulated Radioactive Wastes

dc.contributor.author Erdogan, Cem
dc.contributor.author Bengisu, Murat
dc.contributor.author Erenturk, Sema Akyil
dc.date.accessioned 2023-06-16T14:11:11Z
dc.date.available 2023-06-16T14:11:11Z
dc.date.issued 2014
dc.description.abstract Lead borate based glass formulations with high chemical durability and lower melting temperatures compared to the currently used glasses were developed as candidates for the vitrification of radioactive waste. Properties including chemical durability, glass transformation temperature, and melting temperature were analyzed. The chemical durability of PbO-B2O3 glasses with PbO contents ranging from 30 to 80 mol% was determined. An average dissolution rate of 0.2 g m(-2) day(-1) was obtained for the composition 80PbO center dot 20B(2) O-3. These glasses were studied under simulation conditions and showed good potential as a vitrification matrix for radioactive waste management. Clear vitrified waste products containing up to 30 mol% SrO and 25 mol% Cs2O could be obtained. Leaching rates are about hundred times higher in low PbO glasses compared to high PbO glasses. These results are encouraging since they open up new horizons in the development of low melting temperature lead borate glass for waste immobilization applications. (C) 2013 Elsevier B.V. All rights reserved. en_US
dc.description.sponsorship Ege University, Scientific Research Projects Commission [09NBE003] en_US
dc.description.sponsorship This study was financially supported by the Ege University, Scientific Research Projects Commission (Project No: 09NBE003). en_US
dc.identifier.doi 10.1016/j.jnucmat.2013.10.025
dc.identifier.issn 0022-3115
dc.identifier.issn 1873-4820
dc.identifier.scopus 2-s2.0-84889665501
dc.identifier.uri https://doi.org/10.1016/j.jnucmat.2013.10.025
dc.identifier.uri https://hdl.handle.net/20.500.14365/1303
dc.language.iso en en_US
dc.publisher Elsevier Science Bv en_US
dc.relation.ispartof Journal of Nuclear Materıals en_US
dc.rights info:eu-repo/semantics/closedAccess en_US
dc.subject Lithium-Borate Glasses en_US
dc.subject Liquid Waste en_US
dc.subject Lead-Borate en_US
dc.subject Borosilicate Glass en_US
dc.subject Silicate-Glasses en_US
dc.subject Vitrification en_US
dc.subject Stability en_US
dc.subject Viscosity en_US
dc.subject Behavior en_US
dc.subject Systems en_US
dc.title Chemical Durability and Structural Analysis of Pbo-B2o3 Glasses and Testing for Simulated Radioactive Wastes en_US
dc.type Article en_US
dspace.entity.type Publication
gdc.author.id Bengisu, Murat/0000-0001-6814-5861
gdc.author.id ERENTURK, Sema/0000-0001-9938-1285
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gdc.author.wosid Bengisu, Murat/AAY-3983-2020
gdc.author.wosid ERENTURK, Sema/O-1053-2013
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gdc.description.department İzmir Ekonomi Üniversitesi en_US
gdc.description.departmenttemp [Erdogan, Cem] Ege Univ, Inst Nucl Sci, TR-35100 Izmir, Turkey; [Bengisu, Murat] Izmir Univ Econ, Dept Ind Design, TR-35330 Izmir, Turkey; [Erenturk, Sema Akyil] Istanbul Tech Univ, Energy Inst, TR-34469 Istanbul, Turkey en_US
gdc.description.endpage 164 en_US
gdc.description.issue 1.Mar en_US
gdc.description.publicationcategory Makale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı en_US
gdc.description.scopusquality Q2
gdc.description.startpage 154 en_US
gdc.description.volume 445 en_US
gdc.description.wosquality Q1
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gdc.opencitations.count 34
gdc.plumx.crossrefcites 17
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gdc.virtual.author Bengisu, Murat
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