DC Field | Value | Language |
---|---|---|
dc.contributor.author | KIM, WOONG KEE | - |
dc.contributor.author | Shim, J.H. | - |
dc.contributor.author | MASSOUD, KAVIANY | - |
dc.date.accessioned | 2018-06-15T05:23:10Z | - |
dc.date.available | 2018-06-15T05:23:10Z | - |
dc.date.created | 2017-12-21 | - |
dc.date.issued | 2017-04 | - |
dc.identifier.issn | 0022-3115 | - |
dc.identifier.uri | https://oasis.postech.ac.kr/handle/2014.oak/50420 | - |
dc.description.abstract | Predicting the fate of accident-melted nuclear fuel-cladding requires the understanding of the thermophysical properties which are lacking or have large scatter due to high-temperature experimental challenges. Using equilibrium classical molecular dynamics (MD), we predict the properties of melted UO2 and ZrO2 and compare them with the available experimental data and the predictive models. The existing interatomic potential models have been developed mainly for the polymorphic solid phases of these oxides, so they cannot be used to predict all the properties accurately. We compare and decipher the distinctions of those MD predictions using the specific property-related autocorrelation decays. The predicted properties are density, specific heat, heat of fusion, compressibility, viscosity, surface tension, and the molecular and electronic thermal conductivities. After the comparisons, we provide readily usable temperature-dependent correlations (including UO2-ZrO2 compounds, i.e. corium melt). (C) 2017 Elsevier B.V. All rights reserved. | - |
dc.language | English | - |
dc.publisher | ELSEVIER SCIENCE BV | - |
dc.relation.isPartOf | Journal of Nuclear Materials | - |
dc.subject | THERMAL-CONDUCTIVITY | - |
dc.subject | COULOMBIC SYSTEMS | - |
dc.subject | SHORT-RANGE | - |
dc.subject | VISCOSITY | - |
dc.subject | PRESSURE | - |
dc.subject | SIMULATIONS | - |
dc.subject | EQUATION | - |
dc.subject | PHASE | - |
dc.subject | ARGON | - |
dc.subject | STATE | - |
dc.title | Thermophysical properties of liquid UO2, ZrO2 and corium by molecular dynamics and predictive models | - |
dc.type | Article | - |
dc.identifier.doi | 10.1016/j.jnucmat.2017.04.030 | - |
dc.type.rims | ART | - |
dc.identifier.bibliographicCitation | Journal of Nuclear Materials, v.491, pp.126 - 137 | - |
dc.identifier.wosid | 000404306700014 | - |
dc.date.tcdate | 2019-02-01 | - |
dc.citation.endPage | 137 | - |
dc.citation.startPage | 126 | - |
dc.citation.title | Journal of Nuclear Materials | - |
dc.citation.volume | 491 | - |
dc.contributor.affiliatedAuthor | KIM, WOONG KEE | - |
dc.contributor.affiliatedAuthor | Shim, J.H. | - |
dc.contributor.affiliatedAuthor | MASSOUD, KAVIANY | - |
dc.identifier.scopusid | 2-s2.0-85019154787 | - |
dc.description.journalClass | 1 | - |
dc.description.journalClass | 1 | - |
dc.description.wostc | 3 | - |
dc.type.docType | Article | - |
dc.subject.keywordPlus | THERMAL-CONDUCTIVITY | - |
dc.subject.keywordPlus | COULOMBIC SYSTEMS | - |
dc.subject.keywordPlus | SHORT-RANGE | - |
dc.subject.keywordPlus | VISCOSITY | - |
dc.subject.keywordPlus | PRESSURE | - |
dc.subject.keywordPlus | SIMULATIONS | - |
dc.subject.keywordPlus | EQUATION | - |
dc.subject.keywordPlus | PHASE | - |
dc.subject.keywordPlus | ARGON | - |
dc.subject.keywordPlus | STATE | - |
dc.subject.keywordAuthor | Molten (liquid) corium | - |
dc.subject.keywordAuthor | Molten (liquid) UO2 | - |
dc.subject.keywordAuthor | Molten (liquid) ZrO2 | - |
dc.subject.keywordAuthor | Classical molecular dynamics | - |
dc.subject.keywordAuthor | Density | - |
dc.subject.keywordAuthor | Specific heat | - |
dc.subject.keywordAuthor | Heat of fusion | - |
dc.subject.keywordAuthor | Compressibility | - |
dc.subject.keywordAuthor | Viscosity | - |
dc.subject.keywordAuthor | Surface tension | - |
dc.subject.keywordAuthor | Thermal conductivity | - |
dc.relation.journalWebOfScienceCategory | Materials Science, Multidisciplinary | - |
dc.relation.journalWebOfScienceCategory | Nuclear Science & Technology | - |
dc.description.journalRegisteredClass | scie | - |
dc.description.journalRegisteredClass | scopus | - |
dc.relation.journalResearchArea | Materials Science | - |
dc.relation.journalResearchArea | Nuclear Science & Technology | - |
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