Thermal-hydraulic Analysis in the Pool of PGSFR including the Shielding

Various design issues relate to this region, and one of them is thermal-hydraulic behavior when shielding exists inside the reactor vessel. The shielding is used for the blockage of the radiation emitted by the reactor core. The shielding is installed at the Intermediate Heat eXchanger (IHX), core shroud, and redan region at the top of core. However, this structure disturbs the normal flow path and heat transfer of the primary heat transfer system. In this study, the multi-dimensional thermal-hydraulic characteristics in the pool of PGSFR including the shielding are analyzed. Also these results are compared to a case in which no shielding is installed. A thermal-hydraulic analysis in the pool of the PGSFR considering the shielding structure are performed using STAR-CCM+. The internal major components of the pool inside are modeled, and calculations are performed with a normal operation condition. Also, these results are compared to a no shielding case. The flow and temperature changes owing to the shielding structure at a redan inside are shown, but the overall flow and temperature distributions in both cases are substantially similar. Also the physical properties such as the flow rate, temperature, and static pressure at each major point are almost the same. These results are utilized in the arrangement of the reactor internal structure and design of the shielding structure