Thermal Performance Analysis of Low Temperature Differential Flow Heat Transfer Process in HFETR Irradiation Device
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摘要: 针对高通量工程试验堆(HFETR)内的某特定辐照装置进行研究分析。采用蒙特卡洛程序描述不同材料在不同轴向高度处的释热情况,利用STAR-CCM+程序建立了热工模型,并通过实测数据验证了模型的准确性,在给定工况下,热电偶测点温度计算值与实测值的偏差为2.3%。研究发现,在不考虑辐照装置堵头组件短管径向位置和轴向位置变化的情况下,通过改变热电偶的数量和排布,可能会在低温差流动换热过程中引起1%~4%的温度测量偏差。本文研究揭示了辐照装置中低温差流动换热过程的测量偏差问题,可以为提高温度测量的准确性,以及HFETR安全运行和工程设计提供关键的参考依据。Abstract: In this paper, a specific irradiation device in the High Flux Engineering Test Reactor (HFETR) is studied and analyzed. The Monte Carlo code is used to describe the heat release of different materials at different axial heights. The thermal model is established by using the code STAR-CCM+, and the accuracy of the model is verified by the measured data. Under given conditions, the deviation between the calculated temperature of thermocouple measuring point and the measured value is 2.3%. It is found that the temperature measurement deviation of 1%-4% may be caused in the process of low temperature differential flow heat transfer by changing the number and arrangement of thermocouples without considering the radial and axial position changes of the short tube of the plug assembly of the irradiation device. In this paper, the measurement deviation of low temperature difference flow heat transfer process in irradiation device is revealed, which can provide a key reference for improving the accuracy of temperature measurement and the safe operation and engineering design of HFETR.
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表 1 网格无关性验证
Table 1. Mesh Independence Verification
参数 网格1 网格2 网格3 网格数/万 1933 2465 4126 出口热电偶
测点温度/℃42.30 42.31 42.31 表 2 实测值与计算值比较
Table 2. Comparison of Measured and Calculated Values
参数 入口平均温度/℃ 出口平均温度/℃ 流量/(t·h−1) 压降/MPa 实测值 37.3 42.2 15.7 0.2 计算值 37.3 42.3 15.7 0.2 -
[1] 邓才玉,邱立青,王振东,等. HFETR堆芯及φ63辐照孔道γ释热研究[J]. 核动力工程,2007, 28(6): 97-100. [2] 朱磊,张腾飞,孙寿华,等. HFETR三维堆芯输运燃料管理程序的应用[J]. 核动力工程,2015, 36(6): 10-13. doi: 10.13832/j.jnpe.2015.06.0010 [3] 杨文华,张亮,斯俊平,等. 燃料试样堆内辐照温度设计与实验研究[J]. 核动力工程,2018, 39(6): 43-48. doi: 10.13832/j.jnpe.2018.06.0043 [4] 杨文华,童明炎,孙胜. 模块式套管型随堆辐照考验装置Ansys CFX热工分析[J]. 核动力工程,2013, 34(4): 153-156. [5] 曾科,陶文铨,贾斗南,等. HFETR燃料元件稳态三维流场和温度场数值模拟程序的研制和应用[J]. 核动力工程,2003, 24(S2): 30-33. [6] 张维忠,秋穗正,曾科,等. 高通量工程试验堆堆芯流量分配计算[J]. 核动力工程,2001, 22(2): 97-100,112.