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dc.contributor.author Noh, Seung Hyo -
dc.contributor.author Kwak, Do Hyun -
dc.contributor.author Lee, Juseung -
dc.contributor.author Kang, Joon Hee -
dc.contributor.author Han, Byung Chan -
dc.date.accessioned 2021-04-26T04:35:34Z -
dc.date.available 2021-04-26T04:35:34Z -
dc.date.created 2018-03-29 -
dc.date.issued 2014-03 -
dc.identifier.issn 0374-4884 -
dc.identifier.uri http://hdl.handle.net/20.500.11750/13365 -
dc.description.abstract We utilized first-principles density-functional-theory (DFT) calculations to evaluate the thermodynamic feasibility of a pyroprocessing methodology for reducing the volume of high-level radioactive materials and recycling spent nuclear fuels. The thermodynamic properties of transuranium elements (Pu, Np and Cm) were obtained in electrochemical equilibrium with a LiCl-KCl molten salt as ionic phases and as adsorbates on a W(110) surface. To accomplish the goal, we rigorously calculated the double layer interface structures on an atomic resolution, on the thermodynamically most stable configurations on W(110) surfaces and the chemical activities of the transuranium elements for various coverages of those elements. Our results indicated that the electrodeposition process was very sensitive to the atomic level structures of Cl ions at the double-layer interface. Our studies are easily expandable to general electrochemical applications involving strong redox reactions of transition metals in non-aqueous solutions. © 2014 The Korean Physical Society. -
dc.language English -
dc.publisher Springer -
dc.title First-principles calculations of the thermodynamic properties of transuranium elements in a molten salt medium -
dc.type Article -
dc.identifier.doi 10.3938/JKPS.64.806 -
dc.identifier.scopusid 2-s2.0-84898481111 -
dc.identifier.bibliographicCitation Journal of the Korean Physical Society, v.64, no.6, pp.806 - 812 -
dc.description.isOpenAccess FALSE -
dc.subject.keywordAuthor First principles -
dc.subject.keywordAuthor Density functional theory -
dc.subject.keywordAuthor Recycling spent nuclear fuels -
dc.subject.keywordAuthor Molten salt -
dc.subject.keywordAuthor Pyroprocess -
dc.subject.keywordPlus ELECTROCHEMICAL STABILITY -
dc.subject.keywordPlus URANIUM -
dc.subject.keywordPlus FUEL -
dc.subject.keywordPlus AM -
dc.subject.keywordPlus NP -
dc.subject.keywordPlus PU -
dc.citation.endPage 812 -
dc.citation.number 6 -
dc.citation.startPage 806 -
dc.citation.title Journal of the Korean Physical Society -
dc.citation.volume 64 -
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Department of Energy Science and Engineering Energy Systems Engineering 1. Journal Articles

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