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안상준

Ahn, Sangjoon
UNIST RAdioactive NUclear Materials Lab.
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dc.citation.conferencePlace US -
dc.citation.conferencePlace Orlando -
dc.citation.title 2012 TMS Annual Meeting & Exhibition -
dc.contributor.author Ahn, Sangjoon -
dc.contributor.author Irukuvarghula, Sandeep -
dc.contributor.author McDeavitt, Sean M. -
dc.date.accessioned 2023-12-20T02:08:52Z -
dc.date.available 2023-12-20T02:08:52Z -
dc.date.created 2015-08-11 -
dc.date.issued 2012-03-12 -
dc.description.abstract Uranium – 10 wt% zirconium (U-10Zr) alloy nuclear fuels have been used for many decades and new variations are under consideration ranging from U-5Zr to U-50Zr. The thermophysical behavior of the uranium-zirconium system has been revisited using differential scanning calorimetry (DSC) and other methods. Alloys containing 0.1, 2, 5, 10, 20, 30, and 50 wt% zirconium were prepared by melt-casting ~40 g samples in yttrium oxide crucibles. The phase transitions observed using DSC analyses are in general agreement with the established phase diagram with a few notable exceptions that may, in part, be due to impurities. Most notably, the transition from the α(U)+γ phase field to the β(U)+γ phase field at ~662°C was never observed in these experiments. This observation is consistent with earlier experimental assessments of the U-Zr binary phase diagram as compared with the more recent computational assessments. -
dc.identifier.bibliographicCitation 2012 TMS Annual Meeting & Exhibition -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/34441 -
dc.language 영어 -
dc.publisher The Minerals, Metals & Materials Society (TMS) -
dc.title Thermodynamic assessment of the uranium-zirconium alloy system for nuclear energy applications -
dc.type Conference Paper -
dc.date.conferenceDate 2012-03-11 -

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