Adaptación y aplicación del código TRACE para el análisis de transitorios en diseños de reactores rápidos refrigerados por plomo

Lead-cooled Fast Reactor (LFR) has been identified as one of promising future reactor concepts in the technology roadmap of the Generation IV International Forum (GIF) as well as in the Deployment Strategy of the European Sustainable Nuclear Industrial Initiative (ESNII), both aiming at improved sustainability, enhanced safety, economic competitiveness, and proliferation resistance. This new nuclear reactor concept requires the developments of computational tools to be applied in design and safety assessments to confirm improved inherent and passive safety features of this design. One approach to this issue is to modify the current computational codes developed for the simulation of Light Water Reactors towards their applicability for the new designs. This paper reports on the performed modifications of the TRACE system code to make it applicable to LFR safety assessments. The capabilities of the modified code are demonstrated on series of benchmark exercises performed versus other safety analyses codes.

LAZARO CHUECA Aurelio;  AMMIRABILE Luca;  MARTORELL S.; 

2015-12-10

Sociedad Nuclear Española

JRC98241

1137-2885,   

http://www.sne.es/es/recursos/revista-nuclear-espana,    https://publications.jrc.ec.europa.eu/repository/handle/JRC98241,