Seria: Seminarium Zakładu Energetyki Jądrowej i Analiz Środowiska (UZ3)

Prelegent i afiliacja: Hisham Elgendy NCBJ

Data: 28.01.2025 godz. 11:30

Miejsce: sala 172, bud. 39 (Cyfronet, III piętro)

Streszczenie: The presentation focuses on the enhancements made in thermal-hydraulic modeling for Dual Fluid Reactor (DFR) demonstrators, with an emphasis on the impact of using a variable turbulent Prandtl number. The research presented integrates Kays correlation to address the limitations of traditional approaches, which use a constant Prandtl number and often lead to inaccuracies in heat transfer predictions for low-Prandtl-number liquids. The study demonstrates how the variable turbulent Prandtl number significantly improves the accuracy of simulations, offering more precise predictions for heat transfer, temperature distribution, and flow dynamics within the DFR. Simulations were conducted using Reynolds numbers ranging from 15,000 to 250,000, representing various operating conditions in the reactor. The results reveal critical insights into uneven flow distributions and temperature variations, highlighting areas of high turbulence and potential hotspots that could impact reactor safety and efficiency. The findings also underscore the importance of model selection in computational fluid dynamics (CFD) analysis for advanced reactor designs. This presentation will explore the methodology, key findings, and potential applications of these modeling improvements for next-generation nuclear reactors.