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Lee, Deokjung
Computational Reactor physics & Experiment Lab.
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dc.citation.endPage 1672 -
dc.citation.number 12 -
dc.citation.startPage 1662 -
dc.citation.title INTERNATIONAL JOURNAL OF ENERGY RESEARCH -
dc.citation.volume 40 -
dc.contributor.author Tak, Taewoo -
dc.contributor.author Zheng, Youqi -
dc.contributor.author Lee, Deokjung -
dc.contributor.author Kim, TK -
dc.date.accessioned 2023-12-21T23:11:03Z -
dc.date.available 2023-12-21T23:11:03Z -
dc.date.created 2016-09-09 -
dc.date.issued 2016-10 -
dc.description.abstract SUMMARY: This paper presents a design study of power shape flattening for an optimized ultra-long cycle fast reactor with a power rate of 1000MWe in order to mitigate the power peaking issue and improve the safety with a lower maximum neutron flux and reactivity swing. There are variations in the core designs by loading thorium fuel or zoning fuels in the blanket region and the bottom driver region of ultra-long cycle fast reactor with a power rate of 1000MWe. While it has lower breeding performance in a fast breeder reactor, thorium fuel is one of the promising fuel options for future reactors because of its abundance and its safety characteristics. It has been confirmed that the thorium fuels, when loaded into the center region of a reactor core, lower the power peaking factor from 1.64 to 1.25 after 20years and achieves a more flattened radial power distribution. This consequently reduces the maximum neutron flux and the speed of the active core moving from 3.0cm/year to 2.5cm/year on the average over the 60-year reactor operation. It has been successfully demonstrated that the three-zone core is the most optimized core, has the most flattened radial power shape, and is without any compromise in the nature of long cycle core, from the neutronics point of view, in terms of average discharge burnup and breeding ratio. -
dc.identifier.bibliographicCitation INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.40, no.12, pp.1662 - 1672 -
dc.identifier.doi 10.1002/er.3552 -
dc.identifier.issn 0363-907X -
dc.identifier.scopusid 2-s2.0-85028263234 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/20422 -
dc.identifier.url http://onlinelibrary.wiley.com/doi/10.1002/er.3552/abstract -
dc.identifier.wosid 000384967500006 -
dc.language 영어 -
dc.publisher WILEY-BLACKWELL -
dc.title Power flattening study of ultra-long cycle fast reactor using thorium fuel -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Energy & Fuels; Nuclear Science & Technology -
dc.relation.journalResearchArea Energy & Fuels; Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor ultra-long cycle fast reactor -
dc.subject.keywordAuthor power flattening -
dc.subject.keywordAuthor thorium -
dc.subject.keywordAuthor fuel zoning -
dc.subject.keywordPlus WEAPON GRADE PLUTONIUM -
dc.subject.keywordPlus CANDU REACTOR -
dc.subject.keywordPlus BURN-UP -
dc.subject.keywordPlus CORE -
dc.subject.keywordPlus SUSTAINABILITY -
dc.subject.keywordPlus DESIGN -
dc.subject.keywordPlus BUNDLE -
dc.subject.keywordPlus CODE -

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