Validation of CATHARE-3 system code for sodium two-phase flow application r&d path and simulation of key-tests from SIENA program
Résumé
Sodium Fast Reactors (SFRs) are being considered by several leading nuclearized countries as the most promising technology for next generation of nuclear reactors (Gen IV). In that frame, RetD programs are being conducted to enhance their safety. It is the role of system codes, such as CATHARE-3, to provide a fair balance of the actual safety gain for some severe scenarios that are postulated, such as an Unprotected Loss Of Flow (ULOF).While monophasic simulations with the CATHARE-3 system code are seen today to be reliable, sodium two-phase flow models are still under development and validation process. This paper reports the recent progress made in those fields.First, some key two-phase flow closure laws that are currently considered by CATHARE-3 are summarized. They include some new fluid mechanics correlations that were established thanks to the SENSAS air/water program which was featuring a full-scale subassembly (S/A) mock-up which geometry was consistent with the low void reactor concepts (S/A upper sodium plenum). The developed correlations proved to be efficient in simulating some sodium boiling key-experiments from the French GR-19 and Japanese SIENA-37 80's programs. It is also reported some likely limits of the code current models, especially concerning prediction of dry-out occurrence. In order to support the validation of these closure laws, new experimental programs are required. Their targeted features are briefly described in this document.
Origine : Fichiers produits par l'(les) auteur(s)
Loading...