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Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.endPage 27 -
dc.citation.number 1 -
dc.citation.startPage 16 -
dc.citation.title NUCLEAR TECHNOLOGY -
dc.citation.volume 170 -
dc.contributor.author Bang, In Cheol -
dc.contributor.author Kim, Ji Hyun -
dc.date.accessioned 2023-12-22T07:10:48Z -
dc.date.available 2023-12-22T07:10:48Z -
dc.date.created 2013-06-05 -
dc.date.issued 2010-04 -
dc.description.abstract Nanofluids including metal or metal-oxide nanoparticles have shown improved thermal performance compared to water. Introducing zinc into a water-containing component of the primary system of a boiling water reactor or pressurized water reactor nuclear power plant is known to prevent the deposition of radioactive cobalt and to reduce the possible susceptibility of component materials to corrosion. Also, it is well known that silicon carbide (SiC) is a promising material for advanced reactors. Therefore, preparations of zinc oxide (ZnO) and SiC nanofluids have been used in diverse methods to reduce inconsistency of nanofluid performance. Thermal-fluid characterizations were carried out under the control of the preparation methods. In addition, indirect checks by contact angle measurements of depositions have shown that ZnO and SiC nanofluids as a self-recovering/healing coating solution can contribute to advanced nuclear safety systems in terms of the critical heat flux margin. The results show that more efforts are needed to develop the! nanofluid formulation to tailor the desired properties. -
dc.identifier.bibliographicCitation NUCLEAR TECHNOLOGY, v.170, no.1, pp.16 - 27 -
dc.identifier.issn 0029-5450 -
dc.identifier.scopusid 2-s2.0-77950990699 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/3042 -
dc.identifier.url http://www.scopus.com/inward/record.url?partnerID=HzOxMe3b&scp=77950990699 -
dc.identifier.wosid 000275924900003 -
dc.language 영어 -
dc.publisher AMER NUCLEAR SOC -
dc.title Thermal-fluid characterizations of zno and sic nanofluids for advanced nuclear power plants -
dc.type Article -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -

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