BROWSE

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Sohn, Dong-Seong
Innovative Nuclear FUEL(INFUEL)
Research Interests
  • Nuclear fuel design
  • Nuclear fuel
  • Nuclear system
  • Performance analysis

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Thermal Conductivity Modeling of U-Mo/Al Dispersion Fuel

DC Field Value Language
dc.contributor.author Kim, Yeon Soo ko
dc.contributor.author Cho, Byoung Jin ko
dc.contributor.author Sohn, Dong-Seong ko
dc.contributor.author Park, Jong Man ko
dc.date.available 2015-08-10T07:46:58Z -
dc.date.created 2015-07-29 ko
dc.date.issued 2015-11 ko
dc.identifier.citation JOURNAL OF NUCLEAR MATERIALS, v.466, pp.576 - 582 ko
dc.identifier.issn 0022-3115 ko
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/13382 -
dc.description.abstract A dataset for the thermal conductivity of U-Mo/Al dispersion fuel made available by KAERI was reanalyzed. Using this dataset, an analytical model was obtained by expanding the Bruggeman model. The newly developed model considers thermal resistances at the interfaces between the U-Mo particles and Al matrix and the bonding between Al and Al in the Al matrix. The interfacial resistances are expressed as functions of U-Mo particle size and Al grain size that were empirically obtained by data fitting to the measured data. The new model was validated against an independently measured dataset by ANL. ko
dc.description.statementofresponsibility close -
dc.language 영어 ko
dc.publisher ELSEVIER SCIENCE BV ko
dc.title Thermal Conductivity Modeling of U-Mo/Al Dispersion Fuel ko
dc.type ARTICLE ko
dc.identifier.scopusid 2-s2.0-84941368570 ko
dc.identifier.wosid 000364883400069 ko
dc.type.rims ART ko
dc.description.wostc 0 *
dc.description.scopustc 0 *
dc.date.tcdate 2015-12-28 *
dc.date.scptcdate 2015-11-04 *
dc.identifier.doi 10.1016/j.jnucmat.2015.08.051 ko
dc.identifier.url http://www.sciencedirect.com/science/article/pii/S0022311515301872 ko
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