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On component isolation of conceptual advanced reactors

  • Shrestha, Samyog (Lyles School of Civil Engineering, Purdue University) ;
  • Kurt, Efe G. (Idaho National Laboratory) ;
  • Prakash, Arun (Lyles School of Civil Engineering, Purdue University) ;
  • Irfanoglu, Ayhan (Lyles School of Civil Engineering, Purdue University)
  • 투고 : 2021.11.13
  • 심사 : 2022.02.11
  • 발행 : 2022.08.25

초록

Implementation of component isolation in nuclear industry is challenging due to gaps in research and the lack of specific guidelines. In this study, parameters affecting component-level isolation of advanced reactor vessels are identified based on a representative numerical model with explicit consideration of nonlinear soil-structure interaction (SSI). The objective of this study is to evaluate the effectiveness of, and to identify potential limitations of using conventional friction pendulum bearings to seismically isolate vessels. It is found that slender vessels or components are particularly vulnerable to rotational accelerations at the isolation interface, which are caused by rotation of the sub-structure and by excitation of higher modes in the horizontal direction of the seismically isolated system. Component isolation is found to be more effective for relatively stiffer vessels and at sites with stiff soil. Considering that conventional isolators are deficient in resisting axial tension, it is observed that the optimum location for supporting a component to achieve seismic isolation, is at a cross-sectional plane passing through the center of mass of the vessel. These findings are corroborated by numerous simulations of the response of seismically isolated reactor vessels at different nuclear power plant sites subject to a variety of ground motions.

키워드

과제정보

This research was supported in part by the Batelle Energy Alliance, LLC, Contract No. 212848, and by the Idaho National Laboratory as operated by Battelle Energy Alliance, LLC under Contract DE-AC07-05ID14517.

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