A comparative assessment of independent thermal-hydraulic models for research reactors: The RSG-GAS case

Modelling of void formation in the subcooled boiling regime in the athlet code to simulate flow instability for research reactors

A. Hainoun, E. Hicken, J. Wolters · Nuclear Engineering and Design · 1996 · 89 citations

Athlet Code, Engineering, Physics +10

Flow blockage analysis of a channel in a typical material test reactor core

Qing Lü, Suizheng Qiu, G.H. Su · Nuclear Engineering and Design · 2008 · 59 citations

Flow Blockage Analysis, Engineering, Mechanical Engineering +7

RELAP5/3.2 assessment against low pressure onset of flow instability in parallel heated channels

Tewfik Hamidouche, A Bousbia Salah · Annals of Nuclear Energy · 2006 · 46 citations

Unsteady Flow, Engineering, Heat Exchanger +10

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

Patrícia A.L. Reis, Antonella Lombardi Costa, Cláubia Pereira et al. · Annals of Nuclear Energy · 2010 · 37 citations

Engineering, Nuclear Physics, Relap5 Model +3

Thermal hydraulic analysis of Syrian MNSR research reactor using RELAP5/Mod3.2 code

H. Omar, N. Ghazi, F. Alhabit et al. · Annals of Nuclear Energy · 2010 · 23 citations

Core Thermal Hydraulics, Engineering, Thermal Hydraulics +8