Numerical Simulations of Upper Plenum Thermal-Hydraulics of Monju Reactor Vessel Using High Resolution Mesh Models  

作　　者：Hiroaki Ohira Kei Honda Masutake Sotsu 

机构地区：[1]Japan Atomic Energy Agency, Tsuruga, Fukui, 919-1279 Japan

出　　处：《Journal of Energy and Power Engineering》2013年第4期679-688,共10页能源与动力工程（美国大卫英文）

摘　　要：In order to evaluate the effects of the FHs （flow holes） on the inner barrel, which were installed in the upper plenum of the Monju reactor vessel, a high resolution meshes around the FHs was constructed. Using this model, it was mainly clear that in the 40% rated operational conditions, the shape of the FHs on the inner barrel did not change largely to the upper plenum thermal-hydraulics. The effect of the FHs on the honeycomb structure in the upper structure was also investigated in these calculations. The results indicated that the height of thermal stratification interface became lower than that evaluated from the test data.

关 键 词：Monju reactor vessel upper plenum THERMAL-HYDRAULICS numerical simulation flow holes. 

分 类 号：TL33[核科学技术—核技术及应用] TL351.6