The French program of CEA, IPSN, EDF and FRAMATOME for the Next Generation of Thermal Hydraulic Codes

This paper deals with proposals for thermal-hydraulic research applied to nuclear reactors. After an evaluation of the challenges in terms of the competitiveness and safety of nuclear energy, areas are identified where increased knowledge and advances in thermal-hydraulics are expected. They are in two complementary directions: the improvement of the two-fluid model by inclusion of additional transport equations and the development of the simulation of the fine scales of the flow. The greater computing efficiency can be fully used if the modeling is enhanced, i.e. it becomes more generic end flexible. Recommendations are made for the development of instrumentation and definition of new experiments able to provide the needed information. An outline is given for the progression of the program from present day tools to future tools based on advanced two-fluid model and modeling of local phenomena. (authors)