• Title/Summary/Keyword: Annular Cylindrical Fuel Rod

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Vibration Characteristic Analysis of an Annular Cylindrical PWR Fuel Rod according to the Cross-sectional Dimensions and the Span Length (가압경수로용 환형 실린더 연료봉의 단면치수와 스팬길이에 따른 진동특성해석)

  • Lee, Kang-Hee;Kim, Jae-Yong;Lee, Yung-Ho;Yoon, Kyung-Ho;Kim, Hyung-Kyu
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2007.05a
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    • pp.197-201
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    • 2007
  • Vibration characteristics of an annular 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.

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Dynamic Stability Analysis of Annular Cylindrical Fuel Rod in Axial Flow (축류에 놓인 환형 실린더 연료봉의 동적 안정성 기초해석)

  • Lee, Kang-Hee;Kim, Hyung-Kyu;Yoon, Kyung-Ho;Lee, Young-Ho;Kim, Jae-Yong
    • 한국전산유체공학회:학술대회논문집
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    • 2008.03b
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    • pp.264-267
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    • 2008
  • Dual-cooled fuel with inner and outer flow channel was proposed for high burup, next generation nuclear fuel design. The annular cylinder of dual cooled fuel has higher structural strength compared to the conventional one, but also have concerns about flow induced vibration due to an additional flow of inner channel and the difference of flow velocity in between inner and outer channel. In this study, the dynamic stability of flexible, annular cylinder was evaluated according to the flow variation and compared to the that of the conventional PWR fuel rod. Centrifugal and Coriolis force by the additional flow in the inner channel were added in the dynamic equation of flexible beam in uniform, external, and axial flow. Complex eigenfrequency was calculated by the finite element method. Stability margin of annular cylinder compared to the solid cylinder and change of the dynamic characteristic are presented and discussed as a analysis results.

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Vibration Characteristic Analysis of a Duel-cooled Fuel Rod according to the Cross-sectional Dimensions and the Span Length (이중냉각 연료봉의 단면치수와 스팬길이에 따른 진동특성해석)

  • Lee, Kang-Hee;Kim, Jae-Yong;Lee, Yung-Ho;Yoon, Kyung-Ho;Kim, Hyung-Kyu
    • Transactions of the Korean Society for Noise and Vibration Engineering
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    • v.17 no.9
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    • pp.819-825
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    • 2007
  • 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.