The aim of this study is to evaluate the structural effects (in terms of “global response”) induced by a severe earthquake in a liquid metal reactor main safety relevant structures and components. According to the international safety and design guidelines and to the stress tests requirements for the safety track the effects induced by a ‘beyond design basis’ earthquake (BDBE) event, like the one occurred at Fukushima, should be analyzed in order to evaluate or re-assess the nuclear power plant safety margin. The proposed study is intended to preliminary analyze the structural effects of Liquid Metal cooled Fast Reactor types subjected to a BDBE by means of an appropriate dynamic FEM code. To the purposes, it was considered a lead cooled system (e.g. ELSY/ALFLRED projects) taking into account suitable hypotheses to characterize the dynamic behaviour of the lead fluid and of the reactor building and vessel structures. A great attention was focused too on the arisen hydrodynamic forces and the coupling effects between fluid and structures (fluid-structure interaction and sloshing phenomenon) that may impair the resistance and/or operating capabilities of the reactor structures. The obtained preliminary results were analyzed with the intent also to check the facility general safety margins and to contribute to a step of the safety optimization of the mentioned systems

Preliminary evaluation of the Fluid-Structure Interaction effects in a LFR

2012

Abstract

The aim of this study is to evaluate the structural effects (in terms of “global response”) induced by a severe earthquake in a liquid metal reactor main safety relevant structures and components. According to the international safety and design guidelines and to the stress tests requirements for the safety track the effects induced by a ‘beyond design basis’ earthquake (BDBE) event, like the one occurred at Fukushima, should be analyzed in order to evaluate or re-assess the nuclear power plant safety margin. The proposed study is intended to preliminary analyze the structural effects of Liquid Metal cooled Fast Reactor types subjected to a BDBE by means of an appropriate dynamic FEM code. To the purposes, it was considered a lead cooled system (e.g. ELSY/ALFLRED projects) taking into account suitable hypotheses to characterize the dynamic behaviour of the lead fluid and of the reactor building and vessel structures. A great attention was focused too on the arisen hydrodynamic forces and the coupling effects between fluid and structures (fluid-structure interaction and sloshing phenomenon) that may impair the resistance and/or operating capabilities of the reactor structures. The obtained preliminary results were analyzed with the intent also to check the facility general safety margins and to contribute to a step of the safety optimization of the mentioned systems
Rapporto tecnico;Generation IV reactors;Analisi di sicurezza
File in questo prodotto:
File Dimensione Formato  
XCIRTEN-LP3-012.pdf

accesso aperto

Licenza: Creative commons
Dimensione 1.31 MB
Formato Adobe PDF
1.31 MB Adobe PDF Visualizza/Apri
RdS-2012-072 Frontespizio.pdf

accesso aperto

Licenza: Creative commons
Dimensione 191.17 kB
Formato Adobe PDF
191.17 kB Adobe PDF Visualizza/Apri

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/7476
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
social impact