BELLA: a multi-point dynamics code for safety-informed design of fast reactors

Author:

Bortot S.,Suvdantsetseg E.,Wallenius J.

Funder

VINNMER Marie Curie

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

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.

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