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MODAL TESTING AND MODEL UPDATING OF A REAL SCALE NUCLEAR FUEL ROD
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  • MODAL TESTING AND MODEL UPDATING OF A REAL SCALE NUCLEAR FUEL ROD
  • MODAL TESTING AND MODEL UPDATING OF A REAL SCALE NUCLEAR FUEL ROD
저자명
Park. Nam-Gyu,Rhee. Hui-Nam,Moon. Hoy-Ik,Jang. Young-Ki,Jeon. Sang-Youn,Kim. Jae-Ik
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2009년|41권 6호|pp.821-830 (10 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

In this paper, modal testing and finite element modeling results to identify the modal parameters of a nuclear fuel rod as well as its cladding tube are discussed. A vertically standing full-size cladding tube and a fuel rod with lead pellets were used in the modal testing. As excessive flow-induced vibration causes a failure in fuel rods, such as fretting wear, the vibration level of fuel rods should be low enough to prevent failure of these components. Because vibration amplitude can be estimated based on the modal parameters, the dynamic characteristics must be determined during the design process. Therefore, finite element models are developed based on the test results. The effect of a lumped mass attached to a cladding tube model was identified during the finite element model optimization process. Unlike a cladding tube model, the density of a fuel rod with pellets cannot be determined in a straightforward manner because pellets do not move in the same phase with the cladding tube motion. The density of a fuel rod with lead pellets was determined by comparing natural frequency ratio between the cladding tube and the rod. Thus, an improved fuel rod finite element model was developed based on the updated cladding tube model and an estimated fuel rod density considering the lead pellets. It is shown that the entire pellet mass does not contribute to the fuel rod dynamics; rather, they are only partially responsible for the fuel rod dynamic behavior.