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Development and application of a comprehensive model of a lead-cooled fast reactor using the FAST code system

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Abstract

The purpose of this work was to develop a comprehensive model of a lead-cooled fast reactor and to apply it to the transient analysis of this reactor. The executive branch of the European Union is pursuing several ideas for advanced reactors, including a design called the European Lead-cooled System (ELSY). This design is being developed within the frame of the Lead-cooled European Advanced DEmonstration Reactor (LEADER) project. The FAST Reactors Group at the Paul Scherrer Institut has been at the forefront of fast reactor research in general and has developed a code capable of analyzing the behavior of the European Commission’s new design ideas in-depth. This study used the group’s code and previous experience with ELSY to develop this model.
Original languageEnglish
Pages (from-to)699-700
Number of pages2
JournalTransactions of the American Nuclear Society
Volume105
StatePublished - 2011
Externally publishedYes
Event2011 ANS Annual Winter Meeting and Embedded Topical Meetings: 1st ANS SMR 2011 Conference and Young Professionals Congress 2011 - Washington, DC, United States
Duration: Oct 30 2011Nov 3 2011

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