scholarly journals Fragility analysis of nonproportionally damped inelastic MDOF structural systems exposed to stochastic seismic excitation

2020 ◽  
Vol 226 ◽  
pp. 106129 ◽  
Author(s):  
Ioannis P. Mitseas ◽  
Michael Beer
Keyword(s):  
Seismic Excitation ◽  
Fragility Analysis ◽  
Structural Systems

Robust Design Optimization of Structural Systems Under Evolutionary Stochastic Seismic Excitation

2014 ◽  
Author(s):  
Ioannis P. Mitseas ◽  
Ioannis A. Kougioumtzoglou ◽  
Michael Beer ◽  
Edoardo Patelli ◽  
John E. Mottershead
Keyword(s):  
Design Optimization ◽  
Robust Design ◽  
Seismic Excitation ◽  
Robust Design Optimization ◽  
Structural Systems

Seismic Fragility Analysis of Structural Systems

2006 ◽  
Vol 132 (4) ◽  
pp. 385-395 ◽  
Author(s):  
Giorgio Lupoi ◽  
Paolo Franchin ◽  
Alessio Lupoi ◽  
Paolo E. Pinto
Keyword(s):  
Fragility Analysis ◽  
Seismic Fragility ◽  
Structural Systems

Seismic Isolation of the IRIS Nuclear Plant

2009 ◽  
Author(s):  
Massimo Forni ◽  
Alessandro Poggianti ◽  
Fosco Bianchi ◽  
Giuseppe Forasassi ◽  
Rosa Lo Frano ◽  
...  
Keyword(s):  
Seismic Isolation ◽  
Seismic Analysis ◽  
Wide Spectrum ◽  
Seismic Excitation ◽  
Fragility Analysis ◽  
Pressurized Water ◽  
Isolation System ◽  
Order Of Magnitude ◽  
Safety Features ◽  
The Impact

The safety-by-design™ approach adopted for the design of the International Reactor Innovative and Secure (IRIS) resulted in the elimination by design of some of the main accident scenarios classically applicable to Pressurized Water Reactors (PWR) and to the reduction of either consequences or frequency of the remaining classical at-power accident initiators. As a result of such strategy the Core Damage Frequency (CDF) from at-power internal initiating events was reduced to the 10−8/ry order of magnitude, thus elevating CDF from external events (seismic above all) to an even more significant contributor than what currently experienced in the existing PWR fleet. The same safety-by-design™ approach was then exported from the design of the IRIS reactor and of its safety systems to the design of the IRIS Nuclear Steam Supply System (NSSS) building, with the goal of reducing the impact of seismically induced scenarios. The small footprint of the IRIS NSSS building, which includes all Engineered Safety Features (ESF), all the emergency heat sink and all the required support systems makes the idea of seismic isolation of the entire nuclear island a relatively easy and economically competitive solution. The seismically isolated IRIS NSSS building dramatically reduces the seismic excitation perceived by the reactor vessel, the containment structure and all the main IRIS ESF components, thus virtually eliminating the seismic-induced CDF. This solution is also contributing to the standardization of the IRIS plant, with a single design compatible with a variety of sites covering a wide spectrum of seismic conditions. The conceptual IRIS seismic isolation system is herein presented, along with a selection of the preliminary seismic analyses confirming the drastic reduction of the seismic excitation to the IRIS NSSS building. Along with the adoption of the seismic isolation system, a more refined approach to the computation of the fragility analysis of the components is also being developed, in order to reduce the undue conservatism historically affecting seismic analysis. The new fragility analysis methodology will be particularly focused on the analysis of the isolators themselves, which will now be the limiting components in the evaluation of the overall seismic induced CDF.

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