Numerical Simulation on Temperature Distribution of Steam Generator under Tube Plugging Conditions

In the 150-MWe Korean prototype SFR, a oncethrough type, shell-and-tube heat exchanger with straight vertical tubes was adopted for steam generators. Reliable operation of the steam generators has been a key issue through operating experience of foreign sodium-cooled fast reactors because it is one of the most important components deciding the plant availability and reliability. The temperature differences between parts of the 196-MWt large scale steam generator during operation have to be carefully estimated because it has a number of long and straight tubes. In KAERI, numerical thermal hydraulic analyses for PGSFR SG were carried out to select the porosity of the flow distributors at the inlet plenum and assess the sodium and tube temperatures during normal operation. This work focuses on a numerical study on the temperature distribution at tube bundle of the steam generator for PGSFR with the STAR-CCM+ CFD package coupled with the HSGSA code. A numerical study on the temperature distribution at tube bundle of the steam generator for PGSFR with the STAR-CCM+ CFD package coupled with the HSGSA code. In particular, the simulations under various plugged tube conditions were carried out to evaluate the effect of the tube plugging on the temperature distribution. Based on the results of this work, the mechanical structure analysis of the PGSFR steam generator will be carried out to evaluate the integrity of the component.