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Science and Technology of Nuclear Installations
Volume 2009 (2009), Article ID 214512, 14 pages
Review Article

Review of Available Data for Validation of Nuresim Two-Phase CFD Software Applied to CHF Investigations

1Commissariat à l’Énergie Atomique (CEA), DEN-DER-SSTH, 17 Rue des Martyrs, 38054 Grenoble, France
2Reactor Technology Division, Physics Department, Royal Institute of Technology (KTH), AlbaNova University center, 106 91 Stockholm, Sweden
3Électricité de France (EDF) R&D, Mécanique des Fluides Energie et Environnement, 6 quai Watier, 78401 Chatou, France
4Department of Nuclear Energy and Safety, Thermal-Hydraulics Laboratory, Paul Scherrer Institute (PSI), CH-5232 Villigen, Switzerland
5Forschungszentrum Dresden-Rossendorf (FZD) P.O.Box 510119, D-01314 Dresden, Germany
6Department of Mechanics, Nuclear and Production Engineering – DIMNP, Università di Pisa, 2, Via Diotisalvi, 56100 PISA, Italy
7Department of Thermal-Hydraulic Analyses, Nuclear Research Institute Rez plc (NRI), 25068 Rez, Czech Republic
8Josef Stefan Institute (JSI), Jamova 39, 1000 Ljubljana, Slovenia
9KFKI Atomic Energy Research Institute, Theoretical Thermohydraulics, Research Group, 1525 Budapest, Hungary

Received 24 January 2008; Accepted 23 May 2008

Academic Editor: Iztok Tiselj

Copyright © 2009 D. Bestion et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


The NURESIM Project of the 6th European Framework Program initiated the development of a new-generation common European Standard Software Platform for nuclear reactor simulation. The thermal-hydraulic subproject aims at improving the understanding and the predictive capabilities of the simulation tools for key two-phase flow thermal-hydraulic processes such as the critical heat flux (CHF). As part of a multi-scale analysis of reactor thermal-hydraulics, a two-phase CFD tool is developed to allow zooming on local processes. Current industrial methods for CHF mainly use the sub-channel analysis and empirical CHF correlations based on large scale experiments having the real geometry of a reactor assembly. Two-phase CFD is used here for understanding some boiling flow processes, for helping new fuel assembly design, and for developing better CHF predictions in both PWR and BWR. This paper presents a review of experimental data which can be used for validation of the two-phase CFD application to CHF investigations. The phenomenology of DNB and Dry-Out are detailed identifying all basic flow processes which require a specific modeling in CFD tool. The resulting modeling program of work is given and the current state-of-the-art of the modeling within the NURESIM project is presented.