期刊文献+

钠冷快堆燃料组件流道优化设计数值模拟 被引量:2

下载PDF
导出
摘要 本文采用计算流体力学(CFD)方法针对不同流通横截面的7根棒束组成的快堆燃料组件进行数值模拟,分析绕丝直径与六角管内对边距设置对组件热工水力性能的影响。结果表明,绕丝对冷却剂具有强烈的搅混作用,在起到定位作用的同时,为热平衡提供驱动力。通过改变燃料组件流道结构,即采用外圈小直径绕丝并缩小内对边距的设置,可以对冷却剂在不同子通道中的流量进行重新分配,具有更好的热工水力性能。 This paper uses computational fluid dynamics(CFD)method to simulate the fast reactor fuel assemblies composed of 7 bundles with different flow cross sections,and analyzes the influence of the diameter of the wire-wrap and the setting of the margin in the hexagonal tube on the thermal hydraulic performance of the assemblies.The results show that the wire-wrap has a strong mixing effect on the coolant,and provides a driving force for the heat balance while positioning.By changing the fuel assembly flow path structure,that is,the setting of small diameter wire-wrap with outer ring and narrowing inner-to-edge distance is adopted.,the flow rate of the coolant in different sub-channels can be redistributed,and the thermal hydraulic performance is better.
出处 《科技视界》 2019年第12期1-3,68,共4页 Science & Technology Vision
关键词 快堆 绕丝 六角管对边距 热工水力 CFD Fast reactor Wire wrap Hexagonal pipe to margin Thermal hydraulics CFD
  • 相关文献

参考文献2

二级参考文献13

  • 1陈炳德,熊万玉,王小军.计算流体动力学在燃料组件热工水力性能分析和格架研制中的应用[J].核动力工程,2004,25(5):403-407. 被引量:7
  • 2赵洪章,岳春国,李进贤.基于Fluent的导弹气动特性计算[J].弹箭与制导学报,2007,27(2):203-205. 被引量:35
  • 3刘一哲 喻宏.中国实验快堆单盒燃料组件内冷却剂流场温度场数值模拟.原子能科学技术,2007,41:230-234.
  • 4GAJAPATHY R, VELUSAMY K, SELVARAJ P, et al. CFD investigation of helical wire-wrapped 7 pin fuel bundle and the challenges in modeling fullscale 217 pin bundle[J]. Nuclear Engineering and Design, 2007, 237:2 332-2 342.
  • 5RAZA W, KIM K Y. Comparative analysis of flow and convective heat transfer between 7-pin and 19-pin wirewrapped fuel assemblies[J]. Journal of Nuclear Science and Technology, 2008, 45: 653-661.
  • 6PENIGUEL C, RUPP I, JUHEL J, et al. Three dimensional conjugated heat transfer analysis in sodium fast reactor wire-wrapped fuel assembly [C]//Proceedings of ICAPP 2009. Tokyo, Ja- pan: [s. n.], 2009.
  • 7NATESAN K, SUNDARARAJAN T, NARASIM A, et al. Turbulent flow simulation in a wire wrap rod bundle of an LMFBR[J]. Nuclear En- gineering and Design, 2010, 240:1 063- 1 072.
  • 8IKEDA K, HOSHI M. Development of Mitsub- ishi high thermal performance grid: CFD applica- bility for thermal hydraulic design[J]. JSME In- ternational Journal Series B: Fluids and Thermal Engineering, 2002, 45(3) : 586-591.
  • 9McCLUSKY H L, HOLLOWAY M V. Devel opment of swirling flow in a rod bundle subchan- nel[J].Journal of Fluids Engineering Transac- tions of the ASME, 2002, 124(3): 747 -755.
  • 10HOLLOWAY M V, BEASLEY D E. Single phase convective heat transfer in rod bundles[J]. Nuclear Engineering and Design, 2008, 238(4): 848-858.

共引文献10

同被引文献12

引证文献2

二级引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部