1. Sodium thermal-hydraulics in the pool LMFBR primary vessel;Azarian;Nuclear Engineering and Design,1990
2. 3D computation of thermal-hydraulics in a wire-wrapped rod bundle in the natural and mixed convection regimes using the TRIO VF code;Basque,1989
3. Pressure loss and heat exchange in a rod bundle representative of ETDR start-up core: ESTHAIR experiment in hot air similarity;Berthoux,2008
4. European studies on fast reactor core interwrapper flows;Betts,1991
5. CFD investigations of a full scale helical wire-wrapped 61-pin fuel bundle by using the code TRIO_U;Bieder,2009