Analysis of the influence of different heat transfer correlations for HTR helical coil tube bundle steam generators with the system code TRACE

Abstract

For next high temperature reactor projects, e.g. for electricity production or nuclear process heat applications, the steam generator is a crucial component. The typical design consists of a helical coil tube bundle steam generator with several tubes in different tube cylinders connected in parallel. This type of steam generator was a significant component used in the THTR-300. The influence of different heat transfer correlations for the primary side on the steam outlet temperature is being analyzed by the nodal thermal hydraulics code TRACE for the THTR-300 steam generator and compared to experimental data. The results of the standard TRACE code are compared to results with modified Nusselt numbers for the primary side and they will be elaborated in this paper. These modified Nusselt numbers were used for the heat transfer calculations of the THTR-300 steam generator design.