期刊文献+

带有定位格架的超临界反应堆堆芯强制对流换热的数值研究 被引量:12

Numerical Study on Forced Convection in Sub-Channel with Grid Spacer in Supercritical Reactor Core
原文传递
导出
摘要 采用非结构化多面体网格和商业计算流体力学(CFD)软件对两类带有流动强化特征的定位格架对超临界水在反应堆堆芯子通道内流动及换热特性的影响进行数值研究。研究结果表明:定位格架对子通道内超临界水的换热影响显著;在定位格架内部,流通面积减小,流速增加,换热得以有效强化;阻流片型定位格架对子通道中心流体的阻挡和导流能够中和流动阻塞效应,强化其下游窄缝区的局部换热效果;交错叶片型定位格架能够在其下游产生漩涡流,加强相邻子通道间工质的热量和质量交换,强化局部换热;漩涡流也可能导致轴向速度损失,造成局部换热弱化,不利于反应堆的安全性;入口雷诺数Re对交错叶片型定位格架下游局部换热有较大影响。Re较高时,此类定位格架对子通道内局部换热的强化作用更为明显。 Numerical analysis is carded out for the effects of grid spacer on the forced convection of supercritical water in the sub-channels in supercritical reactor core with commercial CFD code using unstructured polygonal mesh. The results show that the grid spacer has great effects on the heat transfer characteristics of supercritical water within sub-channel. The grid spacer with flow-blockage disc can neutralize the aggravated flow chocking effect by blocking and guiding the flow around the sub-channel center and enhance the local heat transfer near the narrow gap region. Obvious swirling flow is created downstream of the grid spacer with split-vans and the heat and mass transfer between adjacent sub-channels is thus enhanced. The swirling flow can also induce velocity deficits and adversely affect the local heat transfer inside a sub-channel. The Re number has obvious effects on the local heat transfer downstream of the grid spacer with split-vans, and the improved heat transfer performance downstream of the grid spacer with split vanes is more pronounced for the higher Reynolds number case.
出处 《核动力工程》 EI CAS CSCD 北大核心 2014年第3期22-25,共4页 Nuclear Power Engineering
基金 国家科技支撑计划项目(2012BAA14B00) 中央高校基本科研业务费专项资金资助(2342013DUT13RC(3)069)
关键词 超临界水 定位格架 流动强化特征 传热特性 子通道 Supercritical water, Grid spacer, Flow enhancing feature, Heat transfer characteristics Sub-channel
  • 相关文献

参考文献5

  • 1Yamagata K, Nishikawa, K, Hasegawa S, et al. Forced convection heat transfer to supercritical water flowing in tubes[J]. International Journal of Heat and Mass Transfer, 1972, 15: 2575-2593.
  • 2Xiaojing Zhu, Qincheng Bi, Dong Yang, et al. An investigation on heat transfer characteristics of different pressure steam-water in vertical upward tube[J]. Nuclear Engineering and Design, 2009, 239(2): 381-388.
  • 3Wang J G, Li H X, Yu S Q, et al. Comparison of the heat transfer characteristics of supercritical pressure water to that of suberitical pressure water in vertically-upward tubes [J]. International Journal of Multiphase Flow, 2011, 37(7): 769-776.
  • 4田瑞峰,毛晓辉,王小军.5×5定位格架棒束通道内三维流场研究[J].核动力工程,2008,29(5):48-51. 被引量:10
  • 5Holloway M V, McClusky H L, Beasley D E. The effect of support grid features on local, single-phase heat transfer measurements in rod bundles[C]. Proc. of HT2003 ASME Summer Heat Transfer Conference, Las Vegas, Nevada, USA, July 21-23, 2003.

二级参考文献3

共引文献9

同被引文献48

  • 1朱宏晔,杨星团,居怀明,姜胜耀.螺旋管内水和蒸汽局部传热特性研究[J].热科学与技术,2012,11(1):27-33. 被引量:8
  • 2周少祥,刘浩,胡三高,梁双印.电站锅炉熵产分析模型及应用[J].工程热物理学报,2015,36(5):927-932. 被引量:2
  • 3熊万玉,陈炳德,肖泽军.棒束定位格架内单相流体三维流场研究[J].原子能科学技术,2005,39(4):326-329. 被引量:13
  • 4程旭.超临界水冷堆是我国水冷堆技术路线的自然发展[J].中国核工业,2007(4):26-28. 被引量:5
  • 5ISHIWATARI Y, HONGO I, OKA Y, et al.Numerical analysis of heat transfer enhancement by grid spacers in supercritical water [C]. The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Kanazawa City, Ishikawa Prefecture, Tartan, 2009.
  • 6YANG J, OKA Y, LIU J, et al. Development of statistical thermal design procedure to engineering uncertainty of super LWR [J]. Journal of Nuclear Science and Technology, 2006, 43 (1) : 32-42.
  • 7YAMAGATA K, NISHIKAWA K, HASEGAWA S, et al, Forced convection heat transfer to super- critical water flowing in tubes [J]. International Journal of Heat and Mass Transfer, 1972, 15: 2575-2593.
  • 8ZHU X J, BI Q C, YANG D, et al. An investiga- tion on heat transfer characteristics of different pressure steam-water in vertical upward tube [J]. Nuclear Engineering and Design, 2009, 239 (2) : 381-388.
  • 9WANGJ G, LIH X, YUSQ, etal. Comparison of the heat transfer characteristics of supercritical pressure water to that of subcritical pressure water in vertically-upward tubes [ J ]. International Journal of Multiphase Flow, 2011, 37 (7): 769- 776.
  • 10YAO S C, HOCHREITER L E, LEECH W J. Heat transfer augmentation in rod bundles near grid spacers[J]. ASME Journal of Heat Transfer, 1982, 104:76-81.

引证文献12

二级引证文献21

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