SINGLE AND TWO-PHASE SODIUM FLOW ANALYSIS FOR TWO TUCOP CABRI TESTS USING THE ASTEC-Na CODE

The development and validation of ASTEC-Na code as a safety code system for severe accident analysis is being performed in the framework of the JASMIN project supported by the European Commission. One of the main tasks of the modelling and validation tasks of this project is devoted to the sodium thermal hydraulic behavior both in single and two-phase regimes. In this paper we present the first ASTEC-Na results of E8 and EFM1 in-pile tests conducted in the CABRI experimental reactor. These two tests are LOF+TOP transients. We present for both CABRI tests a comparison between experimental data and ASTEC-Na results for transient coolant temperatures at different heights, boiling onset time, inlet and outlet flow rate and the evolution of the sodium two-phase front during the boiling time up to TOP onset. Besides, a benchmark is presented comparing ASTEC-Na simulation results with the results of other safety codes such as CATHARE, RELAP5-3D and SAS-SFR