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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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dc.citation.endPage 392 -
dc.citation.number 3 -
dc.citation.startPage 385 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 45 -
dc.contributor.author Choi, Sang Il -
dc.contributor.author Kim, Ji Hyun -
dc.date.accessioned 2023-12-22T03:46:11Z -
dc.date.available 2023-12-22T03:46:11Z -
dc.date.created 2013-08-28 -
dc.date.issued 2013-06 -
dc.description.abstract Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel cladding and guide tubes because they have excellent corrosion and radiation-resistant properties. In the reactor core, zirconium alloys are subjected to high-energy neutron fluence, causing radiation-induced dislocation and growth. To discern a possible correlation between radiation-induced dislocation and growth, characteristics of dislocation and growth in zirconium and its alloys are examined. The radiation-induced dislocation including and dislocation loops is reviewed in various temperature and fluence ranges, and their growth behavior is examined in the same way. To further a fundamental understanding, radiation-induced growth prediction models are briefly reviewed. This research will assist in the design of zirconium based components as well as the safety analysis of various reactor conditions, in both research and commercial reactors. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.45, no.3, pp.385 - 392 -
dc.identifier.doi 10.5516/NET.07.2013.035 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-84879427328 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/4044 -
dc.identifier.url http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=84879427328 -
dc.identifier.wosid 000321469100010 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title RADIATION-INDUCED DISLOCATION AND GROWTH BEHAVIOR OF ZIRCONIUM AND ZIRCONIUM ALLOYS - A REVIEW -
dc.type Article -
dc.description.isOpenAccess TRUE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Zirconium -
dc.subject.keywordAuthor Zircaloy -
dc.subject.keywordAuthor Radiation-induced Dislocation -
dc.subject.keywordAuthor Radiation-induced Growth -
dc.subject.keywordAuthor Radiation Damage Theory -
dc.subject.keywordPlus NEUTRON-IRRADIATED ZIRCONIUM -
dc.subject.keywordPlus SINGLE-CRYSTALS -
dc.subject.keywordPlus ALPHA-ZIRCONIUM -
dc.subject.keywordPlus DIFFUSION -
dc.subject.keywordPlus DAMAGE -
dc.subject.keywordPlus ZIRCALOY -
dc.subject.keywordPlus CREEP -
dc.subject.keywordPlus ANISOTROPY -
dc.subject.keywordPlus MICROSTRUCTURE -
dc.subject.keywordPlus TEXTURE -

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