Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Development of The New Analysis Methodology for Comprehensive Vibration Assessment Program for Reactor Internals

원자로 내부구조물 종합진동평가 고유 해석방법론 개발

  • 고도영 (한국수력원자력(주) 중앙연구원) ;
  • 김규형 (한국수력원자력(주) 중앙연구원)
  • Received : 2023.05.02
  • Accepted : 2023.06.23
  • Published : 2023.06.30
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Abstract

This paper describes a newly-developed analysis methodology in comprehensive vibration assessment program (CVAP) of reactor internals to develop a valid-prototype for the design of nuclear power plants. The new analysis methodology developed in this study will be confirmed through a scale model testing (SMT). Based on the measurements obtained from dynamic pressure transducers in the SMT, a new non-dimensional equation is developed to apply the forcing functions at reactor internals for the prototype. In addition to the new non-dimensional equation, a computational fluid dynamics(CFD) is used to develop the application of the hydraulic loads at reactor internals for the prototype.

Keywords

Acknowledgement

본 연구는 한국수력원자력(KHNP)의 중장기 연구개발 과제로 한국수력원자력 중앙연구원에서 수행되었다.

References

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