Experiment Study of Heat Transfer to Supercritical Water in a Triangular-Lattice Configuration
-
摘要: 在超临界水多功能实验装置上开展了三角布置棒束内超临界水流动传热实验研究，通过实验观测到了通道内棒束周向温度分布不均匀现象和定位格架导致的传热强化现象，获得不同热流密度、质量流量及压力范围内的传热实验数据，拟合得到预测偏差为±15%的三角布置棒束超临界水传热关系式。Abstract: The experimental research of heat transfer to supercritical water in a triangular-lattice configuration has been performed on the supercritical water multipurpose test loop. Circumferential non-uniformed wall temperature distribution and heat transfer enhancement induced by the grids were observed in the bundles. The heat transfer data under conditions of different heat flux, mass flux and pressure were obtained. Finally, an empirical correlation with the prediction deviation of ±15% was developed to predict the supercritical heat transfer behaviors in the triangular-lattice.
-
Key words:
- Supercritical water /
- Flow heat transfer /
- Triangular-lattice /
- Empirical correlation
-
图 4 高度方向壁温的周向分布（P=23 MPa, q=400 kw/m2）
Figure 4. Circumferential Wall Temperature Distribution along the Height (P=23 MPa, q=400 kw/m2)
图 5 超临界不同质量流速下换热系数随主流焓值的变化
Figure 5. Variations of Heat Transfer Coefficients with Bulk Enthalpy at Different Mass Flux under Supercritical Pressure
图 6 超临界不同热流密度下换热系数随主流焓值的变化
Figure 6. Variations of Heat Transfer Coefficients with Bulk Enthalpy at Different Heat Flux under Supercritical Pressure
图 7 超临界Nu新拟合公式预测值与实验值对比
Figure 7. Comparison of Nusselt Numbers between Predictions by New Correlation and Experimental Results of Supercritical Heat Transfer
表 1 实验工况参数范围
Table 1. Scope of Test Parameters
参数名称 参数值 系统压力/MPa 23 质量流率/(kg·m−2·s−1) 800~1600 热流密度/(kW·m−2) 400~700 入口温度/℃ 285~378 
下载: 导出CSV
表 2 实验工况表
Table 2. List of Test Conditions
编号 压力/
MPa质量流速/
(kg·m−2·s−1)功率/
kW热流密度/
(kW·m−2)入口
温度/℃1 23 800 111.68 400 285 2 23 800 111.68 400 360 3 23 800 111.68 400 376 4 23 800 111.68 400 378 5 23 1200 111.68 400 294 6 23 1200 111.68 400 360 7 23 1200 111.68 400 377 8 23 1200 111.68 400 378 9 23 1600 111.68 400 285 10 23 1600 111.68 400 345 11 23 1600 111.68 400 367 12 23 1600 195.45 700 285 13 23 1600 195.45 700 330 14 23 1600 195.45 700 362 15 23 1600 153.56 550 285 16 23 1600 153.56 550 335 17 23 1600 153.56 550 365
下载: 导出CSV
表 3 各测量参数的不确定度
Table 3. Uncertainties of Various Parameters
测量参数 最大误差 加热棒直径 ±0.05 mm 加热棒长度 ±1 mm 系统压力 0.2% 质量流量 0.4% 流体温度 ±0.5℃ 壁面温度 ±0.5℃ 直流电压 ±1% 直流电流 ±1% 换热系数 6.3% Nu 9.1%
下载: 导出CSV
表 4 超临界传热Nu不同计算公式的误差
Table 4. Deviations of Nusselt Numbers between Calculated and Experimental Results of Supercritical Heat Transfer
计算公式 均差/% 均方差/% DB 8.9 58.1 Domin 249.6 550.0 Jackson(1975) −4.0 14.9 Bishop 3.8 9.3 Watts-Chou −12.2 12.3 Petukhov-Kirillov 46.5 187.4 新拟合公式 −0.6 7.5
下载: 导出CSV
-
[1] POLYAKOV A F. Heat transfer under supercritical pressures[J]. Advances in Heat Transfer, 1991, 21(4): 1-53. [2] CHEN W, FANG X, XU Y, et al. An assessment of correlations of forced convection heat transfer to water at supercritical pressure[J]. Annals of Nuclear Energy, 2015, 76(2): 451-460. [3] DITTUS F W, BOELTER L M K. Heat transfer in automobile radiators of the tubular type[J]. International Communications in Heat and Mass Transfer, 1985, 12(1): 3-22. doi: 10.1016/0735-1933(85)90003-X [4] 陈玮玮,方贤德,商辉,等. 超临界压力下竖直管内水的传热关系式研究[J]. 工程热物理学报,2016, 37(1): 104-110. [5] CHENG X, YANG Y, HUANG S. A simplified method for heat transfer prediction of supercritical fluids in circular tubes[J]. Annals of Nuclear Energy, 2009, 36(8): 1120-1128. doi: 10.1016/j.anucene.2009.04.016 [6] SILIN V A, VOZNESENSKY V A, AFROV A M. The light water integral reactor with natural circulation of the coolant at supercritical pressure B-500 SKDI[J]. Nuclear Engineering & Design, 1993, 144(2): 327-336. [7] KIRILLOV P L, OPANASENKO A N, POMETKO R S, et al. Experiment study of heat transfer on rod bundle at super critical parameters of Freon-12: FEI-3075[R]. Russian: Institute for Physics and Power Engineering, 2006. [8] 李虹波,赵萌,顾汉洋,等. 棒束内超临界水传热实验研究[J]. 原子能科学技术,2015, 49(11): 2017-202. doi: 10.7538/yzk.2015.49.10.2017 -
计量
- 文章访问数: 324
- HTML全文浏览量: 146
- PDF下载量: 28
- 被引次数: 0
