Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Modelling of RV Ledge Region for Dynamic Analysis of Coupled Reactor Vessel Internals and Core

  • Jhung, Myung J. (Korea Institute of Nuclear Safety)
  • Published : 1998.04.01
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Abstract

This paper presents the detailed modelling of reactor vessel ledge region for the dynamic analysis of the coupled internals and core model. The dynamic responses due to earthquake and pipe break are calculated using the input motions of reactor vessel taken from Ulchin nuclear power plant units 3 and 4. Two different representations for detailed and simplified models of the RV ledge region are made. The dynamic responses of the reactor internals components are compared between them. Response characteristics are reported and simplified model is suggested for earthquake and pipe break analysis for the future design of the reactor internals.

Keywords

References

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