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dc.citation.conferencePlace US -
dc.citation.conferencePlace San Francisco -
dc.citation.endPage 2125 -
dc.citation.startPage 2120 -
dc.citation.title 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016 -
dc.citation.volume 3 -
dc.contributor.author Lee, Cheolmin -
dc.contributor.author Cho, Taewon -
dc.contributor.author Jeonga, Gwan Yoon -
dc.contributor.author Kim, Mi Jin -
dc.contributor.author Kim, Jihyeon -
dc.contributor.author Lee, Heejae -
dc.contributor.author Mok,Yongkyoon -
dc.contributor.author Sohn, Dong-Seong -
dc.date.accessioned 2023-12-19T21:06:45Z -
dc.date.available 2023-12-19T21:06:45Z -
dc.date.created 2016-09-23 -
dc.date.issued 2016-04-17 -
dc.description.abstract So far, many experiments have been performed to study the performance of the Zirconium alloys during the accident condition, especially LOCA (Loss Of Coolant Accident) (Ref. 1,2,3). Most of the studies performed in the past are based on the experimental results which used Zry- 4 cladding specimens, but the studies which use recently developed zirconium alloys such as ZIRLO, M5, HANA are not many, and the results have some inconsistencies. In this study, high temperature corrosion tests were performed using Zr-1Nb-1Sn-0.1Fe cladding tube specimens. The experiments were performed at 1000-1200°C, the oxidation kinetics and the breakaway oxidation behavior were studied. The data on oxidation kinetics showed closer results with those from the tests by Westinghouse, but the minimum time for the breakaway oxidation was shorter comparing to the results from Westinghouse and ANL. And also, more detailed analysis results on oxidation kinetics and breakaway oxidation are included. -
dc.identifier.bibliographicCitation 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016, v.3, pp.2120 - 2125 -
dc.identifier.isbn 978-151082594-9 -
dc.identifier.scopusid 2-s2.0-84986317460 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/36883 -
dc.language 영어 -
dc.publisher 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016 -
dc.title High temperature oxidation of the Zr-1Nb-1Sn-0.1Fe cladding tube at the temperatures of 1000 - 1200°C -
dc.type Conference Paper -
dc.date.conferenceDate 2016-04-17 -

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