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Comparison of a Practical Fragility Analysis of a Reactor Building with Non-Linear Monte Carlo Simulation

by Toshiyuki Komura, Ohsaki Research Inst, Japan,
Masatoshi Takeda, Ohsaki Research Inst, Japan,
Tadashi Ando, Ohsaki Research Inst, Japan,
Atsushi Onouchi, Ohsaki Research Inst, Japan,



Document Type: Proceeding Paper

Part of: Structural Safety and Reliability

Abstract:

There are several conventional methods to assess seismic safety of nuclear power plants practically. In these methods, non-linear effect of the structural elements is considered with an inelastic energy absorption factor F?. However, since the effect of more realistic non-linearity of a multi-degree-of-freedom system, such as the phenomenon of damage concentration, is not considered in the conventionally estimated factor F?, it is insufficient to apply the factor to such a complex system. One of the authors has proposed a method extending the factor to include the realistic non-linear effect for simple systems. In this paper, in order to examine the applicability of the proposed method for complex systems, the fragility analysis of a typical BWR-type reactor building is performed by using the proposed method and the Monte Carlo simulation. Through the comparison of these results, it is shown that the proposed method is sufficiently applicable to complex systems.

Subject Headings: Failure analysis | Construction methods | Risk management | Nonlinear analysis | Monte Carlo method | Nuclear power | Energy methods

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