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      균일한 축방향 유동에 노출된 핵 연료봉의 진동특성 분석

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      https://www.riss.kr/link?id=A100172782

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      다국어 초록 (Multilingual Abstract)

      Nuclear fuel rods are exposed to axial flow in a reactor, and flow-induced-vibration due to the flow usually causes damage in the fuel rods. Thus a prior knowledge about dynamic behavior of a fuel rod exposed to the flow condition should be provided. This paper shows that dynamic characteristics of a nuclear fuel rod depend on axial flow velocity. Assuming small lateral displacement, the effects of uniform axial flow are investigated. The analytic results show that axial flow generally reduces fuel rod stiffness and raises its damping in normal condition. Also, the critical axial velocities which make the fuel rod behavior unstable were found. That is, solving generalized eigenvalue equation of the fuel rod dynamic system, the eigenvalues with positive real part are detected. Based on the simulation results, on the other hand, it turns out that the ordinary axial flow in nuclear reactors does not affect to stability of a nuclear fuel rod even in the conservative condition.
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      Nuclear fuel rods are exposed to axial flow in a reactor, and flow-induced-vibration due to the flow usually causes damage in the fuel rods. Thus a prior knowledge about dynamic behavior of a fuel rod exposed to the flow condition should be provided. ...

      Nuclear fuel rods are exposed to axial flow in a reactor, and flow-induced-vibration due to the flow usually causes damage in the fuel rods. Thus a prior knowledge about dynamic behavior of a fuel rod exposed to the flow condition should be provided. This paper shows that dynamic characteristics of a nuclear fuel rod depend on axial flow velocity. Assuming small lateral displacement, the effects of uniform axial flow are investigated. The analytic results show that axial flow generally reduces fuel rod stiffness and raises its damping in normal condition. Also, the critical axial velocities which make the fuel rod behavior unstable were found. That is, solving generalized eigenvalue equation of the fuel rod dynamic system, the eigenvalues with positive real part are detected. Based on the simulation results, on the other hand, it turns out that the ordinary axial flow in nuclear reactors does not affect to stability of a nuclear fuel rod even in the conservative condition.

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      참고문헌 (Reference)

      1 "Vibration of Nuclear Fuel Bundles" pp.399~422.

      2 "Parallel Flow Induced Vibration of Fuel Rods" 18 : 253-278, 1972

      3 "Flow-induced Vibration of Power and Process Plant Components" Professional Engineering Publishing 2001

      4 "Eigenvalue Branches and Flutter Modes of a Discontinuous Cantilevered Pipe Conveying Fluid" 14 (14): 1041-1047, 2004

      5 "Dynamics of Flexible Slender Cylinders in Axial Flow Part 1 Theory" 26 (26): 717-736, 1966

      6 "Dynamics of Flexible Slender Cylinders in Axial Flow" (4) : 737-752, 1966

      7 "Analysis of Fluid-elastic Instability in the CE-type Steam Generator Tube" 14 (14): 261-271, 2002

      8 "An Experimental Study on PWR Nuclear Fuel Assembly Vibration" 82-87, 2003

      9 "An Experimental Study of Vibration of Flexible Cylinders Induced by Nominally Axial Flow" pp.127~138.

      1 "Vibration of Nuclear Fuel Bundles" pp.399~422.

      2 "Parallel Flow Induced Vibration of Fuel Rods" 18 : 253-278, 1972

      3 "Flow-induced Vibration of Power and Process Plant Components" Professional Engineering Publishing 2001

      4 "Eigenvalue Branches and Flutter Modes of a Discontinuous Cantilevered Pipe Conveying Fluid" 14 (14): 1041-1047, 2004

      5 "Dynamics of Flexible Slender Cylinders in Axial Flow Part 1 Theory" 26 (26): 717-736, 1966

      6 "Dynamics of Flexible Slender Cylinders in Axial Flow" (4) : 737-752, 1966

      7 "Analysis of Fluid-elastic Instability in the CE-type Steam Generator Tube" 14 (14): 261-271, 2002

      8 "An Experimental Study on PWR Nuclear Fuel Assembly Vibration" 82-87, 2003

      9 "An Experimental Study of Vibration of Flexible Cylinders Induced by Nominally Axial Flow" pp.127~138.

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2026 평가예정 재인증평가 신청대상 (재인증)
      2020-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2017-01-01 평가 등재학술지 유지 (계속평가) KCI등재
      2013-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2010-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-02-05 학회명변경 영문명 : Korean Society For Noise And Vibration Engeering (Ksnve) -> Korean Society for Noise and Vibration Engineering(KSNVE) KCI등재
      2008-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2004-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2001-07-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      1999-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.28 0.28 0.26
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.25 0.23 0.457 0.05
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