Assessment of a RELAP5 model for the IPR-R1 TRIGA research reactor

Code validation and uncertainties in system thermalhydraulics

Francesco Saverio D'Auria, G. M. Galassi · Progress in Nuclear Energy · 1998 · 88 citations

Engineering, Mechanical Engineering, Systems Engineering +14

Modelling of low-pressure subcooled flow boiling using the RELAP5 code

Boštjan Končar, Borut Mavko · Nuclear Engineering and Design · 2003 · 57 citations

Engineering, Mechanical Engineering, Physics +12

Thermal hydraulic analysis of the IPR-R1 TRIGA research reactor using a RELAP5 model

Antonella Lombardi Costa, Patrícia Amélia L. Reis, Cláubia Pereira et al. · Nuclear Engineering and Design · 2010 · 32 citations

Engineering, Mechanical Engineering, Nuclear Engineering +16

Neutronic calculation to the TRIGA Ipr-R1 reactor using the WIMSD4 and CITATION codes

Cláubia Pereira, Rosemary G.P Souza · Annals of Nuclear Energy · 2002 · 27 citations

Engineering, Nuclear Engineering, Physics +14

The effect of code user and boundary conditions on RELAP calculations of MTR research reactor transient scenarios

Ahmed Khedr, Martina Adorni, Francesco Saverio D'Auria · Nuclear Technology and Radiation Protection · 2005 · 19 citations · Full text

Engineering, Nuclear Engineering, Fluid Dynamics +16