Article ID Journal Published Year Pages File Type
6761589 Nuclear Engineering and Design 2015 14 Pages PDF
Abstract
In the frame of an AREVA - KIT cooperation in the years 2008-2013 on R&D issues associated with Innovative sodium cooled fast reactor concepts, several major topics were identified as being of mutual interest to both partners, one of which was the evaluation of severe transient behavior in Sodium-cooled Fast Reactors (SFRs) and the impact of newly conceived mitigation measures. The SFR design taken for the analysis was the SFR(v2b-ST) reactor design, and the system code to be used was selected to be the SIM-SFR code. The transients chosen for evaluation of the efficiency of mitigation measures were the unprotected loss-of-flow (ULOF), the unprotected loss-of-heat-sink (ULOHS) and the unprotected transient-overpower (UTOP).
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Authors
, , , ,