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김희령

Kim, Hee Reyoung
RAdiation and MagnetohydroDynamics Advanced Lab.
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dc.citation.endPage 478 -
dc.citation.number 2 -
dc.citation.startPage 469 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 54 -
dc.contributor.author Kang, Ki Joon -
dc.contributor.author Byun, Jaehoon -
dc.contributor.author Kim, Hee Reyoung -
dc.date.accessioned 2023-12-21T14:38:50Z -
dc.date.available 2023-12-21T14:38:50Z -
dc.date.created 2022-02-03 -
dc.date.issued 2022-02 -
dc.description.abstract Tritium was extracted from tritium-contaminated aluminum samples by heating it in a high-temperature furnace at 200, 300, or 400 °C for 15 h. The extracted tritium was analyzed by using a liquid scintillation counter (LSC); the sample thicknesses were 0.4 and 2 mm. The differences in tritium extraction over time were also investigated by cutting aluminum stick samples into several pieces (1, 5, 10, and 15) with the same thickness, and subsequently heating them. The results revealed that there are most of the hydrated material based on tritium on the surface of aluminum. When the temperature was increased from 200 or 300 °C–400 °C, there are no large differences in the heating duration required for the radioactivity concentration to be lower than the MDA value. Additionally, at the same thickness, because the surface of aluminum is only contaminated to tritiated water, cutting the aluminum samples into several pieces (5, 10, and 15) did not have a substantial effect on the tritium extraction fraction at any of the applied heating temperatures (200, 300, or 400 °C). The proportion of each tritium-release materials (aluminum hydrate based on tritium) were investigated via diverse analyses (LSC, XRD, and SEM-EDS). -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.2, pp.469 - 478 -
dc.identifier.doi 10.1016/j.net.2021.10.023 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-85118146891 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/57157 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S1738573321006070?via%3Dihub -
dc.identifier.wosid 000753340300008 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Tritium extraction in aluminum metal by heating method without melting -
dc.type Article -
dc.description.isOpenAccess TRUE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.description.journalRegisteredClass kci -
dc.subject.keywordAuthor Aluminum contamination -
dc.subject.keywordAuthor Heating pretreatment -
dc.subject.keywordAuthor Tritium radioactivity -
dc.subject.keywordAuthor Tritium extraction -
dc.subject.keywordAuthor Tritium analysis -
dc.subject.keywordPlus ORGANICALLY BOUND TRITIUM -
dc.subject.keywordPlus COMBUSTION -

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