增压室空间
计算流体力学
雷诺平均Navier-Stokes方程
钠冷快堆
湍流
分层(种子)
机械
离散化
计算机科学
核工程
数学
物理
工程类
热力学
数学分析
种子休眠
发芽
生物
植物
休眠
作者
Shuji Ohno,Hiroshi Ohki,Akihiro Sugahara,Hiroyuki Ohshima
摘要
Abstract Validation of a numerical simulation method is carried out for thermal stratification phenomena in the reactor vessel upper plenum of advanced sodium-cooled fast reactors. The study mainly focuses on the fundamental applicability of commercial computational fluid dynamics (CFD) codes as well as an inhouse code to the evaluation of thermal stratification behavior including the simulation methods such as spatial mesh distribution and RANS-type turbulence models in the analyses. Two kinds of thermal stratification tests are used in the validation, which is done for relatively simple- and conventional-type upper plenum geometries with water and sodium as working fluids. Quantitative comparison between the simulation and test results clarifies that when used with a high-order discretization scheme of the convection term, the investigated CFD codes are applicable to evaluations of the basic behaviors of thermal stratification and especially the vertical temperature gradient of the stratification interface, which is important from the viewpoint of structural integrity. No remarkable difference is seen in the simulation results obtained using different RANS turbulence models, namely, the standard kε model, the RNG k-ε model, and the Reynolds stress model. It is further confirmed in a numerical experiment that the distribution of two or more meshes within the stratification interface will lead to accurate simulation of the interface temperature gradient with less than 10% error. KEYWORDS: numerical analysisthermal stratificationturbulence modelsodiumfast reactor
科研通智能强力驱动
Strongly Powered by AbleSci AI