Experiemental Study on Heat Transfer of Supercritical Water in Triangular Channel of Reactor Core with Spacer Grid
-
摘要: 针对带定位格架的超临界水冷堆堆芯垂直上升类三角形子通道，开展超临界水的流动传热试验研究。反应堆堆芯类三角形子通道棒束直径为8 mm、栅距比为1.4，试验参数范围为：热流密度q=200~600 kW/m2、压力P=23~28 MPa、质量流速G=700~1300 kg/(m2·s)。分析了热流密度、压力和质量流速等热工参数对超临界水传热特性的影响。试验结果表明：定位格架处质量流速升高，流体扰动性增强，换热系数提升显著；在超临界压力下，提高压力会导致内壁温度上升，换热系数峰值降低；过高的热流密度会导致换热系数峰值降低，适当减小热流密度可提高换热性能；提高质量流速会导致内壁温度降低，换热系数峰值上升，能够显著提高换热性能。压力变化对定位格架区域传热特性影响较小，适当提升压力可提高系统安全性。Abstract: The experimental study on supercritical water flow heat transfer is carried out for the vertical upward triangular sub-channels in the supercritical water cooled reactor core with spacer grid. The fuel bundle diameter and pitch ratio of this sub-channel used are 8 mm and 1.4 respectively. The parameters adopted in the research include heat flux (q) ranging from 600 kW/m2, pressure (P) ranging from 23-28 MPa, and mass flow rate (G) ranging from 700-1,300 kg/(m2·s). This study analyzes the effect of such thermal parameters as heat flux, pressure and mass flow rate on the heat transfer characteristics of supercritical water. According to the experimental results, with the mass flow rate at the spacer grid increasing, the fluid disturbance increases and the heat transfer coefficient rises significantly; under the supercritical pressure, the inner surface temperature increases with the increasing pressure, and consequently, the peak heat transfer coefficient decreases; as the peak heat transfer coefficient reduces at an excessively high heat flux, the heat transfer performance can be improved when the heat flux is reduced properly; increasing the mass flow rate causes the drop of inner surface temperature and the increase of peak heat transfer coefficient, and thus can significantly improve the heat transfer performance; and the pressure change has little effect on the heat transfer characteristics in the vicinity of spacer grid, and however, the system safety can be improved by increasing the pressure properly.
-
Key words:
- Supercritical water /
- Triangular sub-channel /
- Heat transfer /
- Experimental study
-
图 1 系统布置图
1—水箱；2—调节阀；3—滤网；4—高压柱塞泵；5—孔板流量；6—高效再生式换热器；7—预热段；8—试验段；9—冷却换热器；10—质量流量计；11—数据采集系统
Figure 1. System Layout
图 2 子通道结构及测点布置情况
NO.1—截面1，其余同
Figure 2. Sub-Channel Structure and Layout of Measuring Points
图 3 截面周向测点布置
Figure 3. Layout of Measuring Point in Circumferential Direction of Cross Section
图 4 不同热流密度对换热性能影响
Figure 4. Effect of Different Heat Fluxes on Heat Transfer Performance
图 6 不同质量流速对换热性能影响
Figure 6. Effect of Different Mass Flow Rates on Heat Transfer Performance
表 1 测量参数的不确定度
Table 1. Uncertainties of Parameters Measured
参数 最大不确定度 工质流量 ±0.1% 压力 ±0.15% 工质温度 ±0.4℃ 壁面温度 ±0.5℃ 试验段直径 ±0.03 mm 试验段壁厚 ±0.02 mm 试验电压 ±0.5% 试验电流 ±0.1% 
下载: 导出CSV
-
[1] XU J L, SUN E H, LI M J, et al. Key issues and solution strategies for supercritical carbon dioxide coal fired power plant[J]. Energy, 2018, 157(8): 227-246. [2] YAMAGATA 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(72): 2575-2593. [3] SHITSMANM M E. Impairment of the heat transmission at supercritical pressures[J]. High Temperature, 1963, 1(2): 237-244. [4] WANG W S, BI Q C, GU H F, et al. An investigation on heat transfer to water flowing in vertical upward internally ribbed enhancement tube at supercritical pressure[J]. Advanced Science Letters, 2011, 4(6-7): 2281-2288. [5] PIORO I L, KHARTABILL H F, DUFFEY R B. Heat transfer to supercritical fluids flowing in channels-empirical correlations(survey)[J]. Nuclear Engineering and Design, 2004, 230(1-3): 69-91. doi: 10.1016/j.nucengdes.2003.10.010 [6] WANG J G, Li H X, GUO B, et al. Investigation of forced convection heat transfer of supercritical pressure water in a vertically upward internally ribbed tube[J]. Nuclear Engineering and Design, 2009, 239(10): 1956-1964. doi: 10.1016/j.nucengdes.2009.04.012 [7] ZHU B G, XU J L, WU X M, et al. Supercritical “boiling” number, a new parameter to distinguish two regimes of carbon dioxide heat transfer in tubes[J]. International Journal of Thermal Sciences, 2019, 139(8): 254-266. [8] JIANG P X, LE Z, Xu R N. Experimental study of convective heat transfer of carbon dioxide at supercritical pressures in a horizontal rock fracture and its application to enhanced geothermal systems[J]. Applied Thermal Engineering, 2017, 117: 39-49. doi: 10.1016/j.applthermaleng.2017.01.078 [9] CHENG X, KUANG B, YANG Y H. Numerical analysis of heat transfer in supercritical water cooled flow channels[J]. Nuclear Engineering and Design, 2007, 237(3): 240-252. doi: 10.1016/j.nucengdes.2006.06.011 [10] ZHU X J, MOROOKA S, OKA Y. Numerical investigation of grid spacer effect on heat transfer of supercritical water flows in a tight rod bundle[J]. International Journal of Thermal Sciences, 2014, 76(2): 245-257. [11] YANG X B, SU G H, TIAN W X, et al. Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition[J]. Annals of Nuclear Energy, 2010, 37(12): 1723-1734. doi: 10.1016/j.anucene.2010.07.008 [12] ZHU X J, MOROOKA S, OKA Y. Numercial investigation of grid spacer effect on heat transfer of supercritical water flows in a tight rod bundle[J]. International Journal of Thermal Sciences, 2014, 76(76): 245-257. [13] 李永亮,曾小康,黄志刚,等. 简单通道内超临界水传热特性实验研究[J]. 核动力工程,2013, 34(1): 101-107. doi: 10.3969/j.issn.0258-0926.2013.01.022 [14] WU G, BI Q C, YANG Z D, et al. Experimental investigation of heat transfer for supercritical pressure water flowing in vertical annular channels[J]. Nuclear Engineering and Design, 2011, 241(9): 4045-4054. doi: 10.1016/j.nucengdes.2011.07.007 [15] YANG Z D, BI Q C, WANG H, et al. Experiment of heat transfer to supercritical water flowing in vertical annular channels[J]. Heat Transfer, 2013, 135(4): 676-709. [16] 王为术,路统,赵鹏飞,等. 超临界水冷堆类四边形子通道内超临界水的传热试验研究[J]. 中国电机工程学报,2014, 34(20): 3356-3361. [17] 赵鹏飞. 反应堆类四边形子通道内超临界水流动传热特性研究[D]. 郑州: 华北水利水电大学, 2014. [18] 路统. 超临界水冷堆类三角形子通道内超临界水传热的试验研究[D]. 郑州: 华北水利水电大学. 2015. [19] 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): 2017-2023. doi: 10.7538/yzk.2015.49.10.2017 [20] 何斯琪,顾汉洋,李虹波,等. 带格架四棒束超临界水流动传热数值分析[J]. 原子能科学技术,2014, 48(2): 257-262. doi: 10.7538/yzk.2014.48.02.0257 [21] WANG H, BI Q C, YANG Z D, et al. Experimental and numerical study on the enhanced effect of spiral spacer to heat transfer of supercritical pressure water in vertical annular channels[J]. Applied Thermal Engineering, 2012, 48(15): 436-445. [22] 干富军,刘达,顾汉洋,等. 棒束通道中格架对传热影响的实验研究[J]. 原子能科学技术,2019, 53(04): 648-653. [23] 许多挺. 环管内超临界水流动传热实验研究及数值计算[D]. 上海: 上海交通大学, 2014. -
图(6) / 表(1)
计量
- 文章访问数: 161
- HTML全文浏览量: 110
- PDF下载量: 19
- 被引次数: 0
