1. CFD prediction of flow and phase distribution in fuel assemblies with spacers, NURETH-7, 1995 Saratoga Springs, New York;Anglart;Nuclear Engineering and Design,1997
2. Experimental study of true void fraction when boiling subcooled water in vertical tubes;Bartolomej;Thermal Engineering,1967
3. Boucker, M., Guelfi, A., Mimouni, S., Péturaud, P., Bestion, D., Hervieu, E., 2006. Towards the prediction of local thermal-hydraulics in real PWR core conditions using NEPTUNE_CFD software. Workshop on Modeling and Measurements of Two-Phase Flows and Heat Transfer in Nuclear Fuel Assemblies, KTH, Stockholm, Sweden 10–11 October 2006.
4. The Favre averaged drag model for turbulence dispersion in Eulerian multi-phase flows;Burns,2004
5. Bubble departure diameter and release frequencies during nucleate pool boiling of water and aqueous NaCl solutions;Ceumern-Lindenstjerna,1977