Article ID Journal Published Year Pages File Type
6759521 Nuclear Engineering and Design 2018 12 Pages PDF
Abstract
The analysis results show that the maximum stress values of these SFSRs and their support frame under seismic loads are within the specified code limits. An impact between the support frame and the adjacent pool wall will not occur because the sliding distance calculated from the nonlinear time history analysis is less than the gap between the two elements. These results confirm that they cannot be overturned but will instead slide under an SSE event. Finally, the seismic fragility analysis results demonstrate that the designed spent fuel storage system has a sufficient seismic margin which exceeds the targeted seismic design level.
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