Experimental and numerical thermal‐hydraulics investigation of a molten salt reactor concept core
26th Symposium of AER on VVER Reactor Physics and Reactor Safety (2016, Helsinki, Finland)
Nuclear applications of computational fluid dynamics
Abstract
EXPERIMENTAL AND NUMERICAL THERMAL-HYDRAULICS INVESTIGATION OF A MOLTEN SALT REACTOR CONCEPT COREBogdán Yamaji, Attila AszódiInstitute of Nuclear Techniques, Budapest University of Technology and Economics tel: +36 1 463 2112 fax: +36 1 463 1954e-mail: yamaji@reak.bme.hu, aszodi@reak.bme.huBudapest, Műegyetem rkp. 9., Hungary 1111ABSTRACTIn the paper measurement results of experimental modelling of a molten salt fast reactor concept will be presented and compared with three-dimensional computational fluid dynamics (CFD) simulation results. The investigated molten salt reactor concept has a homogeneous cylindrical core without any internal structures. Previous measurements and simulation results have shown that this core geometry could be optimized for better thermal-hydraulics characteristics. In case of the original geometry strong unfavourable flow separation could develop. Two regions would form: a slow, stagnating region near the cylindrical wall due to recirculation and a high velocity jet stream. Such a disadvantageous velocity distribution would also lead to unfavourable temperature distribution in the core and it could negatively affect the characteristics of the core from neutronics point of view as well.The experimental investigation was carried out on the scaled and segmented plexiglas model of the molten salt reactor concept. In the scaled and segmented mock-up the working fluid is water. An internal flow distributor plate was designed and installed with the purpose of optimizing the flow field in the core by enhancing its uniformity. Measurement results of the experimental model will be presented and compared to numerical simulation results with the purpose of validating the CFD models. For the non-intrusive flow measurements carried out on the scaled and segmented mock-up particle image velocimetry (PIV) method was applied.26th Symposium of AER on VVER Reactor Physics and Reactor Safety 48 10 – 14 October 2016, Helsinki, Finland