主催: 一般社団法人 日本機械学会
会議名: 第25回 動力・エネルギー技術シンポジウム
開催日: 2021/07/26 - 2021/07/27
The reactor vessel cooling system is a static cooling system that removes decay heat from the core by convection and radiation heat transfer without using dynamic components and is one of the safety systems that constitute the inherent safety features of High Temperature Gas Reacter. However, the natural convection of the gas may cause hot spots on important structures such as the pressure vessel during the cooling using this system. For this reason, a three-dimensional numerical model simulating the High Temperature Test Reacter 1/6 scale model was developed and numerically analyzed. It was found that it is better to use the surface-to-surface model for the radiation model and the k-ε model for the turbulence model. We also examined the effect of adding components to the model. It was found that there was no need to model the cooling pipe.