Open AccessNumerical discretization analysis of a HTR steam generator model for the thermal-hydraulics code trace
Author(s) -
Markus Esch,
Dietrich Knoche,
Antonio Hurtado
Publication year - 2014
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp140ss31e
Subject(s) - thermal hydraulics , nuclear engineering , heat recovery steam generator , boiler (water heating) , pressurized water reactor , heat transfer , mechanical engineering , materials science , mechanics , engineering , physics , waste management , steam turbine
For future high temperature reactor projects, e. g., for electricity production or nuclear process heat applications, the steam generator is a crucial component. A typical design is a helical coil steam generator consisting of several tubes connected in parallel forming cylinders of different diameters. This type of steam generator was a significant component used at the thorium high temperature reactor. In the work presented the temperature profile is being analyzed by the nodal thermal hydraulics code TRACE for the thorium high temperature reactor steam generator. The influence of the nodalization is being investigated within the scope of this study and compared to experimental results from the past. The results of the standard TRACE code are compared to results using a modified Nusselt number for the primary side. The implemented heat transfer correlation was developed within the past German HTR program. This study shows that both TRACE versions are stable and provides a discussion of the nodalization requirements