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안상준

Ahn, Sangjoon
UNIST RAdioactive NUclear Materials Lab.
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dc.citation.endPage 11 -
dc.citation.startPage 6 -
dc.citation.title JOURNAL OF ALLOYS AND COMPOUNDS -
dc.citation.volume 681 -
dc.contributor.author Ahn, Sangjoon -
dc.contributor.author Irukuvarghula, Sandeep -
dc.contributor.author McDeavitt, Sean M. -
dc.date.accessioned 2023-12-21T23:11:37Z -
dc.date.available 2023-12-21T23:11:37Z -
dc.date.created 2016-05-17 -
dc.date.issued 2016-10 -
dc.description.abstract Ion-beam irradiation has been conducted to demonstrate and assess solid phase dependence of fission gas bubble nucleation and growth in metallic nuclear fuels. Differential formation and growth of irradiation-induced voids and bubbles were observed from as-cast uranium-zirconium (U-Zr) alloys including 0.1 and 40 wt% zirconium. The U-Zr alloys were irradiated with 140-keV He+ ions with fluences ranged from 1 × 1014 ions/cm2 to 5 × 1016 ions/cm2. Several larger spherical bubbles (<∼70 nm) were revealed from an irradiated single α-U phase alloy (U-0.1Zr) in which observed bubbles were mobile under 200-keV electron beam of transmission electron microscope (TEM). In-situ mergence and leakage of the bubbles in the uranium-rich alloy was also evident during the observation. In contrast, numerous number of small (∼6 nm) angular voids, or low pressure bubbles, were found in an irradiated δ-UZr2 phase alloy (U-40Zr), in which the radiation-induced nanostructure was stationary throughout the observation. This study may reaffirm higher radiation-susceptibility of the α-U phase than the δ-UZr2 phase, which could strengthen the needs of separate accounting of solid phase effects for metallic fuel performance modeling particularly regarding the fuel restructuring phenomena, such as fission gas swelling and constituent redistribution, since conventional models are commonly adopted homogeneous medium assumption, not in accordance with the results of post-irradiation examinations of used metallic nuclear fuel in which the formation of several concentric phase zone was distinct corresponding to a steep radial temperature gradient in the fuel pin and multiple isotherm lines in the binary phase diagram of U-Zr alloy system. -
dc.identifier.bibliographicCitation JOURNAL OF ALLOYS AND COMPOUNDS, v.681, pp.6 - 11 -
dc.identifier.doi 10.1016/j.jallcom.2016.04.219 -
dc.identifier.issn 0925-8388 -
dc.identifier.scopusid 2-s2.0-84964910418 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/19177 -
dc.identifier.url http://www.sciencedirect.com/science/article/pii/S0925838816311975 -
dc.identifier.wosid 000376443300002 -
dc.language 영어 -
dc.publisher ELSEVIER SCIENCE SA -
dc.title Microstructure of alpha-U and delta-UZr2 phase uranium-zirconium alloys irradiated with 140-keV He+ ion-beam -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Chemistry, Physical; Materials Science, Multidisciplinary; Metallurgy & Metallurgical Engineering -
dc.relation.journalResearchArea Chemistry; Materials Science; Metallurgy & Metallurgical Engineering -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Uranium-zirconium alloy -
dc.subject.keywordAuthor Metallic nuclear fuel -
dc.subject.keywordAuthor Irradiation-induced void and bubble -
dc.subject.keywordAuthor Swelling -
dc.subject.keywordAuthor Ion beam irradiation -
dc.subject.keywordPlus FISSION-GAS BEHAVIOR -
dc.subject.keywordPlus METALLIC FUEL -
dc.subject.keywordPlus ANALYSIS CODE -

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