A study on heat capacity of oxide and nitride nuclear fuels by using Einstein-Debye approximation

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dc.contributor.authorEser, E.
dc.contributor.authorDuyuran, B.
dc.contributor.authorBölükdemir, M. H.
dc.contributor.authorKoç, Hüseyin
dc.date.accessioned2020-01-29T18:54:13Z
dc.date.available2020-01-29T18:54:13Z
dc.date.issued2019
dc.departmentFakülteler, Mühendislik-Mimarlık Fakültesi, Elektrik-Elektronik Mühendisliği Bölümüen_US
dc.description.abstractKnowledge on fuel enthalpy and its temperature derivative, the heat capacity, are important quantities in determination of fuel behavior in normal reactor operation and reactor transients. The aim of this study is to compare the heat capacity of oxide and nitrite fuels by using Einstein-Debye approximation. A simple analytical expression was performed to calculate the heat capacity of fuels. To test the validity and reliability, the calculated formulas were compared to published results for various nuclear fuels including UO2, ThO2, PuO2 and UN. Calculated formulas yielded results in consistent with literature. © 2019en_US
dc.identifier.doi10.1016/j.net.2019.11.012
dc.identifier.issn1738-5733
dc.identifier.scopus2-s2.0-85075821189
dc.identifier.scopusqualityQ1
dc.identifier.urihttps://dx.doi.org/10.1016/j.net.2019.11.012
dc.identifier.urihttps://hdl.handle.net/20.500.12639/1396
dc.identifier.wosWOS:000536288100013
dc.identifier.wosqualityQ1
dc.indekslendigikaynakWeb of Science
dc.indekslendigikaynakScopus
dc.language.isoen
dc.publisherKorean Nuclear Societyen_US
dc.relation.ispartofNuclear Engineering and Technologyen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/openAccessen_US
dc.subjectEinstein-Debye approximationen_US
dc.subjectHeat capacityen_US
dc.subjectNitride fuelen_US
dc.subjectOxide fuelen_US
dc.titleA study on heat capacity of oxide and nitride nuclear fuels by using Einstein-Debye approximationen_US
dc.typeArticle

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