Nuclear Engineering and Technology

  • 제46권5호
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  • Pages.689-698
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  • 2014
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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MODAL CHARACTERISTIC ANALYSIS OF THE APR1400 NUCLEAR REACTOR INTERNALS FOR SEISMIC ANALYSIS

  • 투고 : 2014.02.19
  • 심사 : 2014.04.24
  • 발행 : 2014.10.25
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⟨ 이전 논문 다음 논문 ⟩

초록

Reactor internals are sensitive to dynamic loads such as earthquakes and flow induced vibration. Thus, it is essential to identify the dynamic characteristics to evaluate the seismic integrity of the structures. However, a full-sized system is too large to perform modal experiments, making it difficult to extract data on its modal characteristics. In this research, we constructed a finite element model of the APR1400 reactor internals to identify their modal characteristics. The commercial reactor was selected to reflect the actual boundary conditions. Our FE model was constructed based on scale-similarity analysis and fluid-structure interaction investigations using a fabricated scaled-down model.

키워드

참고문헌

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피인용 문헌

  1. Seismic analysis of nuclear power plants by using three-dimensional finite element models: a review vol.56, pp.1, 2019, https://doi.org/10.1080/00223131.2018.1532846