Preliminary evaluation of the seismic response of the ELSY LFR
Creators
- 1. Department of Mechanical, Nuclear and Production Engineering, University of Pisa, Via Diotisalvi, no2-56126 Pisa (Italy)
Description
Highlights: ► The load bearing capability of the European Lead-cooled System (ELSY) subjected to SSE earthquake was evaluated. ► We adequately simulated the global response and safety margin of ELSY reactor. ► The analyses allowed to represent the seismic demand taking also into account the fluid-structure interaction and sloshing phenomenon. ► In the study the relevance of the isolation technique effectiveness was presented and discussed. ► The results highlighted the reactor integrity is ensured despite some localized yielding stress value. - Abstract: The main goal of the present study is the preliminary evaluation of the seismic demand of a LFR with reference to European Lead System project (ELSY) considered one of the most promising innovative Generation IV reactor. The safety aspects of the ELSY reactor in the event of a Safe Shutdown Earthquake, taking into account also the effects of the possible fluid–structure interaction, have been analyzed. To the purpose to determine the seismic demand, in according with the international rules, a non-linear dynamic analysis method was used with rather refined 3-D model of LFR for the foreseen structural analyses and simulations of the plant and of the reactor internals behaviour. In this report numerical results are presented and discussed highlighting the relevance of the fluid–structure interaction in terms of structural integrity as well as the isolation technique effectiveness, which is expected to increase the safety margin of the reactor structures during a seismic event, if the isolators frequency is far from that of the reactor. The present work has been performed within the 6th European Framework Project.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2011.10.052Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2011.10.052;
- PII
- S0029-5493(11)00930-7;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 242
- Journal Page Range
- p. 361-368
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43074136
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- EARTHQUAKES; FLUID-STRUCTURE INTERACTIONS; LEAD; LIQUID METAL COOLED REACTORS; NONLINEAR PROBLEMS; REACTOR COMPONENTS; REACTOR SAFETY; REACTOR SHUTDOWN; SAFETY MARGINS; STRESSES
- Descriptors DEC
- ELEMENTS; METALS; REACTORS; SAFETY; SEISMIC EVENTS; SHUTDOWN
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.