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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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Variation of the lattice parameter and thermal expansion coefficient of (U,Dy)O-2 as a function of DyO1.5 content

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dc.contributor.author Kim, SH ko
dc.contributor.author Kim, HS ko
dc.contributor.author Lee, YW ko
dc.contributor.author Sohn, Dong-Seong ko
dc.contributor.author Suhr, DS ko
dc.date.available 2014-09-18T02:28:10Z -
dc.date.created 2014-09-17 ko
dc.date.issued 2006-01 ko
dc.identifier.citation JOURNAL OF ALLOYS AND COMPOUNDS, v.407, no.1-2, pp.263 - 267 ko
dc.identifier.issn 0925-8388 ko
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/6198 -
dc.description.abstract Thermal expansions of (U,Dy)O2 solid solutions were investigated between room temperature and 1673 K by using a thermo-mechanical analyzer. The lattice parameter of (U,Dy)O2 pellets is lower than that of UO 2 and it decreases as Dy content increases. The linear thermal expansion and average thermal expansion coefficients of (U,Dy)O2 are higher than that of UO2. For the temperature range from room temperature to 1673 K, the average thermal expansion coefficient values for UO2 and (U0.8Dy0.2)O2 are 10.97 × 10-6 and 11.37 × 10-6 K-1, respectively. ko
dc.description.statementofresponsibility close -
dc.language 영어 ko
dc.publisher ELSEVIER SCIENCE SA ko
dc.title Variation of the lattice parameter and thermal expansion coefficient of (U,Dy)O-2 as a function of DyO1.5 content ko
dc.type ARTICLE ko
dc.identifier.scopusid 2-s2.0-29244443962 ko
dc.identifier.wosid 000234613600042 ko
dc.type.rims ART ko
dc.description.wostc 1 *
dc.description.scopustc 1 *
dc.date.tcdate 2015-05-06 *
dc.date.scptcdate 2014-09-17 *
dc.identifier.doi 10.1016/j.jallcom.2005.05.034 ko
dc.identifier.url http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=29244443962 ko
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