Modelling guidelines for core exit temperature simulations with system codes

SBLOCA with boron dilution in pressurized water reactors. Impact on operation and safety

Jordi Freixa, F. Reventós, C. Pretel et al. · Nuclear Engineering and Design · 2009 · 32 citations

Engineering, Chemical Engineering, Nuclear Engineering +14

Applying UPC Scaling-Up Methodology to the LSTF-PKL Counterpart Test

Víctor Martínez-Quiroga, F. Reventós, Jordi Freixa · Science and Technology of Nuclear Installations · 2014 · 28 citations · Full text

Engineering, Civil Engineering, Quality Assurance +8

Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE

Jordi Freixa, Annalisa Manera · Nuclear Engineering and Design · 2010 · 25 citations

Medicine, Anatomy, Nuclear Instrumentation +1

The Use of System Codes in Scaling Studies: Relevant Techniques for Qualifying NPP Nodalizations for Particular Scenarios

Víctor Martínez-Quiroga, F. Reventós · Science and Technology of Nuclear Installations · 2014 · 22 citations · Full text

Engineering, Nuclear Engineering, Systems Engineering +13

Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation

Jordi Freixa, Taewan Kim, Annalisa Manera · Nuclear Engineering and Design · 2013 · 20 citations

Engineering, Mechanical Engineering, Heat Transfer +16