Seismic response analysis of reactor building and equipment with hazard consistent ground motions using a 3D-FE model

Nishida, Akemi  ; Muramatsu, Ken; Takada, Tsuyoshi*  

R&D on Next-Generation Seismic PRA (NGSPRA) by using 3D vibration simulator is ongoing to evaluate seismic safety performance of nuclear plants with high reliability. Most PRA of structures involve the use of probabilistic schemes such as the scheme using probabilistic seismic hazard and fragility curves. Even when earthquake ground motions (GM) are required in Monte Carlo Simulations (MCS), they are generated to fit the specified response spectra, such as uniform hazard spectra at a specified exceedance probability. These GM, however, are not directly linked with corresponding seismic source characteristics. In this context, the authors propose a methodology based on MCS to reproduce a set of input GM to develop an advanced PRA scheme that can explain the exceedance probability and sequence of functional loss in a nuclear power plant. In this paper, the methodology to reproduce a set of input GM and the analytical results of nuclear plant building using those input GM are shown.