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首页> 外文期刊>Applied thermal engineering: Design, processes, equipment, economics >Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core
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Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core

机译：通过核反应堆卵石床芯对高普朗特数流体流动和对流热传递的实验研究

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摘要

For Fluoride-salt-cooled High-temperature Reactors (FHRs), a pebble bed experimental facility with internal heat generation is set up, using the Dowtherm A as the simulant fluid. Dowtherm A can match the Prandtl number of FLiBe of 520-700 degrees C at a low temperature range of 45-105 degrees C. The effects of inlet temperatures, porosity and mass flow rate are investigated on the flow and convective heat transfer characteristics. A criterion is determined for the flow regime transition from the transitional to turbulent flow. The existing correlations are unable to predict the Blake-type friction factor in the transitional flow and show mixed performance in the turbulent flow. The present empirical correlations generally underestimate the convective heat transfer coefficients of the high-Prandtl-number fluid in the pebble bed. New correlations are proposed for predicting the flow and convective heat transfer coefficients with Prandtl number at 14-19 and Reynolds number at 90-2500.
机译：对于氟化物 - 盐冷却的高温反应器（FHRS），使用Dowermer A A作为模拟液，建立具有内部发热的卵石床实验设施。 Dowtherm A可以将520-700摄氏度的PRANDTL系数匹配在45-105摄氏度的低温范围内。研究了进气温，孔隙率和质量流量的影响，对流动和对流传热特性进行了研究。 确定从过渡到湍流的流动调节器转换的标准。 现有相关性无法预测过渡流程中的布莱克式摩擦系数，并在湍流中显示混合性能。 本实证相关性通常低估了卵石床中的高普兰特数流体的对流传热系数。 提出了新的相关性，用于预测在90-2500的14-19和雷诺数的Prandtl号的流动和对流传热系数。

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