Numerical evaluation of sloshing effects in ELSY innovative nuclear reactor pressure vessels seismic response

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dc.contributor.author Forasassi, G.
dc.contributor.author Lo Frano, R.
dc.date.accessioned 2014-06-27T07:24:54Z
dc.date.available 2014-06-27T07:24:54Z
dc.date.issued 2008
dc.description.abstract Paper presented at the 6th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, South Africa, 30 June - 2 July, 2008. en_US
dc.description.abstract In Europe a great effort has been made in the Lead-Bismuth Eutectic (LBE) technology, for use in the sub-critical reactors, and its natural development is represented by the use of pure lead that is less corrosive, chemically inert and in the foreseen environment has good neutronic and thermal-hydraulic characteristics, therefore it appears to be a suitable coolant for a fast reactor. The main purpose of this study deals with the evaluation of the sloshing dynamic effects of lead coolant during a safety shut down earthquake applied to a conceptual Lead-cooled Fast Reactor (LFR) Generation IV (GEN IV) Nuclear Power Plant design, with reference to the ELSY project system configuration that is under development within the ongoing European 7FW ELSY Program. ELSY is an innovative small size pool-type reactor (600 MWe) cooled by pure lead, characterized by a compact and simple integrated primary circuit; by the way this configuration is favourable from the point of view of the reduction of the seismic loads and of the negative effect of the high lead density. Therefore, the fluid-structure interaction problems and the free oscillations of the heavy metal primary coolant attracted the attention because during a strong motion earthquake the lead surrounding the internals may be accelerated and the so-called hydrodynamic interaction, due to the coolant sloshing, may significantly influence the stress level in the reactor pressure vessel (RPV). To the purpose, the effect of the rigidity of adjacent internals walls and coupling between coolant and vessel are considered An adequate numerical modelling, by means a 3-D finite element model, was set up and used for the foreseen structures dynamic analysis, due to the inability of linear theory to describe accurately the wave’s motion accounting for the complex considered RPV geometrical aspect as well as the material nonlinearities. Numerical results are presented and discussed highlighting the importance of the fluid-structure interaction effects in terms of stress intensity as well as the capacity of internals and vessel walls to withstand wave’s impact and prevent instabilities. en_US
dc.description.librarian vk2014 en_US
dc.format.extent 6 pages en_US
dc.format.medium PDF en_US
dc.identifier.citation Forasassi, G & Lo Frano R 2008, 'Numerical evaluation of sloshing effects in ELSY innovative nuclear reactor pressure vessels seismic response', Paper presented to the 6th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, South Africa, 30 June - 2 July 2008. en_US
dc.identifier.isbn 9781868546916
dc.identifier.uri http://hdl.handle.net/2263/40421
dc.language.iso en en_US
dc.publisher International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics en_US
dc.relation.ispartof HEFAT 2008 en_US
dc.rights University of Pretoria en_US
dc.subject Numerical evaluation en_US
dc.subject Sloshing effects en_US
dc.subject ELSY innovative en_US
dc.subject Nuclear reactor pressure vessels en_US
dc.subject Lead-Bismuth Eutectic en_US
dc.subject LBE en_US
dc.subject Sub-critical reactors en_US
dc.subject Lead-cooled Fast Reactor en_US
dc.subject LFR en_US
dc.subject Nuclear power plant design en_US
dc.subject ELSY project system en_US
dc.subject Reactor pressure vessel en_US
dc.subject RPV en_US
dc.subject 3 D finite element modelliog en_US
dc.title Numerical evaluation of sloshing effects in ELSY innovative nuclear reactor pressure vessels seismic response en_US
dc.type Presentation en_US


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