首页> 外文会议>International Conference on Nuclear Engineering >DEVELOPED A SPACER GRID FOR THE FUTURE PWR FUEL ASSEMBLY BY CONSIDERING THE THERMAL/HYDRAULIC AND MECHANICAL/STRUCTURAL PERFORMANCE
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DEVELOPED A SPACER GRID FOR THE FUTURE PWR FUEL ASSEMBLY BY CONSIDERING THE THERMAL/HYDRAULIC AND MECHANICAL/STRUCTURAL PERFORMANCE

机译:通过考虑热/液压和机械/结构性能,开发了未来PWR燃料组件的间隔网格

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The spacer grid is one of the structural components for the fuel assembly. In order to increase or extend the fuel life cycle, a spacer grid which has a much higher performance from the thermal/hydraulic and mechanical/structural point of view will be needed. From the thermal/hydraulic viewpoint, the CHF margin is very important in order to extend its life. Particularly, the mixing flow or cross flow between the subchannels have to be reinforced for this purpose. From the mechanical/structural viewpoint, the critical strength and the fuel rod support behaviour of a spacer grid are the same as the TH performance improvement for the next generation fuel. A computational fluid dynamics (CFD) analysis was performed to investigate the coolant mixing in a nuclear fuel bundle that is promoted by the mixing vane on the grid spacer. Single and multiple subchannels of one grid span of the fuel bundle were modeled to simulate a 5by5 rod array experiment with the mixing vane. The three-dimensional CFD models were generated by a structured multi-block method. The standard k-ε turbulence model was used in the current CFD simulation since it is practically useful and converges well for the complex turbulent flow in a nuclear fuel bundle. The CFD predictions of the axial and lateral mean flow velocities showed a somewhat larger difference from the experimental results near the spacer but represented the overall characteristics of the coolant mixing well in a nuclear fuel bundle with the mixing vane. Comparison of the single and multiple subchannel predictions shows a good agreement for the flow characteristics in the central subchannel of the rod array. The simulation of the multiple subchannels shows a slightly off-centered swirl in the peripheral subchannels due to the external wall of the rod array. It also shows no significant swirl and crossflow in the wall subchannels and the corner subchannels.
机译:间隔栅格是燃料组件的结构部件之一。为了增加或延伸燃料寿命周期,将需要具有从热/液压和机械/结构观点的具有更高性能的间隔栅格。从热/液压观点来看,CHF边缘非常重要,以延长其生命。特别地,为此目的,必须加强子通道之间的混合流程或交叉流动。从机械/结构观点来看,间隔栅格的临界强度和燃料杆支撑行为与下一代燃料的性能改善相同。进行计算流体动力学(CFD)分析以研究通过在栅极隔离物上促进的核燃料束中的冷却剂混合。为燃料束的一个网格跨度的单个和多个子信道被建模以模拟与混合叶片的5By5杆阵列实验。通过结构化的多块方法生成三维CFD模型。标准K-ε湍流模型用于电流CFD仿真,因为它实际上是有用的,并且在核燃料束中的复杂湍流流量很好地收敛。轴向和横向平均流速的CFD预测从间隔件附近的实验结果表明了一个稍微较大的差异,但是用混合叶片表示在核燃料束中井的冷却剂混合的整体特征。单个和多个子信道预测的比较显示了杆阵列中央子信道中的流特性的良好一致性。由于杆阵列的外壁,多个子通道的模拟显示在外围子信道中的略微偏心涡旋。它还显示了墙壁子通道和角落子信道中的任何重要旋涡和交叉流。

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