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손동성

Sohn, Dong-Seong
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High temperature oxidation of the Zr-1Nb-1Sn-0.1Fe cladding tube at the temperatures of 1000 - 1200°C

Author(s)
Lee, CheolminCho, TaewonJeonga, Gwan YoonKim, Mi JinKim, JihyeonLee, HeejaeMok,YongkyoonSohn, Dong-Seong
Issued Date
2016-04-17
URI
https://scholarworks.unist.ac.kr/handle/201301/36883
Citation
2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016, v.3, pp.2120 - 2125
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.
Publisher
2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016
ISBN
978-151082594-9

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