1. Stability analyses for the European LFR demonstrator;Bortot;Nucl. Eng. Des.,2013
2. Bortot S. et al., Transient Evaluation of a Gen-IV LFR Demonstration Plant through a Lumped Parameter Analysis of Coupled Kinetics and Thermal-hydraulics. Proc. International Congress on Advances in Nuclear Power Plants (ICAPP 10), San Diego, California, USA, 2010.
3. Dynamic performance assessment of MOX and metallic fuel core options for a Gen-IV LFR demonstrator;Bortot;Progr. Nucl. Energy,2011
4. Review and proposal for best-fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations;Bubelis;Nucl. Eng. Des.,2008
5. Cahalan, J.E., Fanning, T.H., 2012. The SAS4A/SASSYS-1 Safety Analysis Code System, ANL/NE-12/4, Argonne National Laboratory.