首页> 外文会议>International conference on nuclear engineering;ICONE-16 >CFD ASSESSMENT OF THE LOCAL HOT CORE TEMPERATURE IN A PEBBLE- BED TYPE VERY HIGH TEMPERATURE REACTOR
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CFD ASSESSMENT OF THE LOCAL HOT CORE TEMPERATURE IN A PEBBLE- BED TYPE VERY HIGH TEMPERATURE REACTOR

机译:卵石型超高温反应器局部热核温度的CFD评估

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Assessment of the local hot core temperature during normal operation in a pebble-bed type of Very High Temperature Reactor (VHTR) has been carried out by using the Computational Fluid Dynamic (CFD) method for which the boundary conditions were obtained from the results of a macroscopic analysis of the core using a system thermal analysis code, GAMMA. Three pebble arrangements are selected, which are Simple Cubic (SC), Body-Centered Cubic (BCC), and Face-Centered Cubic (FCC). Results showed that the SC arrangement having the lowest porosity gives the highest fuel temperature of 1237°C but still below the normal operational fuel limit of 1250°C. Comparison of the CFD results with an empirical correlation was made for the pressure drop and the Nusselt number but there were large differences between them. The benchmark calculation of a pressure drop for packed particles in a square channel indicated that the correlation for the full core used in the system code is not appropriate for the prediction of a local thermal fluid behavior.
机译:在卵石床型超高温反应堆(VHTR)的正常运行过程中,已经通过使用计算流体动力学(CFD)方法对局部热核温度进行了评估,该方法的边界条件是从计算结果中获得的。使用系统热分析代码GAMMA对核心进行宏观分析。选择了三种卵石排列,分别是简单立方(SC),体心立方(BCC)和面心立方(FCC)。结果表明,具有最低孔隙率的SC装置可提供最高燃料温度1237°C,但仍低于正常运行燃料极限1250°C。比较了CFD结果和经验相关的压降和Nusselt值,但两者之间存在较大差异。在方形通道中对填充颗粒的压降进行基准测试表明,系统代码中使用的完整核的相关性不适用于预测局部热流体行为。

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