Core thermal-hydraulics behaviour within the framework of the feasibility studies of the RJH research reactor

The purpose of this work is to give a preliminary evaluation of the thermal-hydraulic behaviour of the reactor Jules Horowitz (RJH project). These performances are evaluated by using computer codes. First a calculation procedure was drawn then the output data have been elaborated. The calculations are performed by using the operating code SIRENE which provides us with the boundary limits of the core. The 3-dimension thermal-hydraulic code FLICA-4 has allowed us to get an accurate behaviour of the core in various operating modes (nominal, accidental, natural convection). This work is only an introduction and further studies have to be led. (A.C.)