当前位置: X-MOL 学术Nucl. Eng. Des. › 论文详情
Our official English website, www.x-mol.net, welcomes your feedback! (Note: you will need to create a separate account there.)
Experimental characterization of boiling two-phase flow structures under BWR core operating conditions
Nuclear Engineering and Design ( IF 1.9 ) Pub Date : 2020-08-01 , DOI: 10.1016/j.nucengdes.2020.110708
J.-M. Le Corre

Abstract Local two-phase flow parameters have been measured at the Westinghouse FRIGG facility in a test fuel bundle under Boiling Water Reactor (BWR) core operating conditions, over a wide range of flow and power (up to critical power). The measurements were performed at end of heated length using sapphire optical probes and Pitot tubes placed in various radial positions of the bundle. By using both instruments simultaneously, the void fraction, mixture velocity, dispersed phase (bubble or drop) characteristic lengths and volumetric interfacial area can be measured. In addition, the identification of two-phase flow regimes can be attempted. The measurements are of particular interest since there is very limited available data in the literature at high pressure relevant to BWR operation. Experimental measurements are reported in this paper covering a range of inlet flow and bundle power relevant to BWR operation, at a system pressure of 70 bar. The dynamic void fluctuations are used to establish two-phase flow regime maps, one based on global parameters (for 1-D applications) and the second based on local parameters (for CFD applications). However, it is discovered that transition flow regimes typically observed at low pressure (cap, slug, etc) are not similarly observed at high pressure. In addition, the measured characteristic lengths of the dispersed phase are reported in bubbly and annular two-phase flow regimes. In view of the results, recommendations are provided for further experimental work and modeling improvements.

中文翻译:

BWR堆芯工况下沸腾两相流结构的实验表征

摘要 在西屋 FRIGG 设施中,在沸水反应堆 (BWR) 堆芯运行条件下,在很宽的流量和功率范围内(达到临界功率),在测试燃料束中测量了局部两相流参数。测量是在加热长度的末端使用蓝宝石光学探头和放置在束的不同径向位置的皮托管进行的。通过同时使用两种仪器,可以测量空隙率、混合物速度、分散相(气泡或液滴)特征长度和体积界面面积。此外,可以尝试识别两相流态。这些测量值特别令人感兴趣,因为与 BWR 操作相关的高压下的可用数据非常有限。本文报告了实验测量结果,涵盖了与 BWR 操作相关的一系列入口流量和束功率,系统压力为 70 bar。动态空隙波动用于建立两相流态图,一个基于全局参数(用于一维应用),第二个基于局部参数(用于 CFD 应用)。然而,发现通常在低压(帽、段塞等)下观察到的过渡流态在高压下没有类似地观察到。此外,在气泡和环形两相流态中报告了分散相的测量特征长度。鉴于结果,为进一步的实验工作和建模改进提供了建议。动态空隙波动用于建立两相流态图,一个基于全局参数(用于一维应用),第二个基于局部参数(用于 CFD 应用)。然而,发现通常在低压(帽、段塞等)下观察到的过渡流态在高压下没有类似地观察到。此外,在气泡和环形两相流态中报告了分散相的测量特征长度。鉴于结果,为进一步的实验工作和建模改进提供了建议。动态空隙波动用于建立两相流态图,一个基于全局参数(用于一维应用),第二个基于局部参数(用于 CFD 应用)。然而,发现通常在低压(帽、段塞等)下观察到的过渡流态在高压下没有类似地观察到。此外,在气泡和环形两相流态中报告了分散相的测量特征长度。鉴于结果,为进一步的实验工作和建模改进提供了建议。发现通常在低压(帽、段塞等)下观察到的过渡流态在高压下观察不到。此外,在气泡和环形两相流态中报告了分散相的测量特征长度。鉴于结果,为进一步的实验工作和建模改进提供了建议。发现通常在低压(帽、段塞等)下观察到的过渡流态在高压下观察不到。此外,在气泡和环形两相流态中报告了分散相的测量特征长度。鉴于结果,为进一步的实验工作和建模改进提供了建议。
更新日期:2020-08-01
down
wechat
bug