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http://dx.doi.org/10.5050/KSNVN.2007.17.9.819

Vibration Characteristic Analysis of a Duel-cooled Fuel Rod according to the Cross-sectional Dimensions and the Span Length  

Lee, Kang-Hee (한국원자력연구원 선진경수로연료개발센터)
Kim, Jae-Yong (한국원자력연구원 선진경수로연료개발센터)
Lee, Yung-Ho (한국원자력연구원 선진경수로연료개발센터)
Yoon, Kyung-Ho (한국원자력연구원 선진경수로연료개발센터)
Kim, Hyung-Kyu (한국원자력연구원 선진경수로연료개발센터)
Publication Information
Transactions of the Korean Society for Noise and Vibration Engineering / v.17, no.9, 2007 , pp. 819-825 More about this Journal
Abstract
Vibration characteristics of an duel-cooling cylindrical fuel rod, which was proposed as a candidate design of fuel's cross section for the ultra-high burnup nuclear fuel, according to the cross-sectional dimensions and the number of supports or the span length were analytically studied. Finite element(FE) modeling for the annular cross sectional fuel was based on the methodology, that have been proven by the test verification, for the conventional PWR nuclear fuel rod. A commercial FEA code, ABAQUS, was used for the FE modeling and analysis. A planar beam element (B21) that uses a linear interpolation was used for the fuel rod and a linear spring element for the spring and dimple of the SG. Natural frequencies and mode shape were calculated according to the preliminary design candidates for the fuel's cross sectional dimension and the number of span. From the analysis results, the design scheme of the annular fuel compatible to the present PWR nuclear reactor core was discussed in terms of the number of supports and fuel's cross section.
Keywords
Duel-cooled Fuel Rod; Natural Frequency; Mode Shape; Cross-sectional Dimension; Span Length; Flow-Induced Vibration; Compatibility;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
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