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- 2015
600 MW超临界W火焰锅炉流动不稳定性数值分析
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Abstract:
建立了适用于超临界锅炉流动不稳定性分析的通用数值计算模型,编写了以Fortran语言为基础的流动不稳定性数值计算程序,对程序进行验证后,采用时域法对600 MW超临界W火焰锅炉的流动不稳定性进行了模拟。计算得到了W火焰锅炉的水动力特性曲线,并研究了系统参数对其动态流动不稳定性的影响。结果表明:该模型对模拟超临界水流动不稳定性具有一定的可靠性;在0.09~0.3 kg/s的流量参数范围内,压降?擦髁刻匦郧?线始终为单值关系,静态流动不稳定性不会发生;当进口压力由25 MPa增大到27 MPa或进口流量由0.091 kg/s增加到0.1 kg/s时,流量脉动的振幅逐渐减小,表明增加进口压力或进口流量锅炉的稳定性提高;当进口阻力系数由10减小到0.5或出口阻力系数由1增大到5时,流量脉动的振幅逐渐增大,表明减小进口阻力系数或增大出口阻力系数锅炉的稳定性降低。
A general numerical computational model suitable for the analysis of supercritical boiler instability was established, and the numerical computational program based on Fortran was developed. Then the flow instability of a 600 MW supercritical W flame boiler was simulated by the time??domain method after the model and code were verified. The curve of pressure drop versus flow rate was obtained and the parametric effects on the dynamic instability of the W flame boiler were analyzed. The results showed that the model is reliable to simulate the supercritical water instability; the curve of pressure drop versus flow rate is always an one??on??one relationship at the flow rate range from 0.09 to 0.3 kg/s, which means the static flow instability does occur; when the inlet pressure increases from 25 to 27 MPa or the inlet flow rate increases from 0.091 to 0.1 kg/s, the amplitude of flow rate oscillation decreases, indicating that increasing inlet pressure or inlet flow rate will improve the boiler’s stability; when the inlet pressure drop coefficient decreases from 10 to 0.5 or the outlet pressure drop coefficient increases from 1 to 5, the amplitude of flow rate oscillation increases, indicating that decreasing the inlet pressure drop coefficient or increasing the outlet pressure drop coefficient will reduce the boiler’s stability
[1] | [1]DURGA P G V, PANDEY M, KALRA M S. Review of research on flow instabilities in natural circulation boiling systems [J]. Progress in Nuclear Energy, 2007, 49(6): 429??451. |
[2] | [13]AMBROSINI W. Assessment of flow stability boundaries in a heated channel with different fluids at supercritical pressure [J]. Annals of Nuclear Energy, 2011, 38(2/3): 615??627. |
[3] | [14]张项飞. 超临界压力下自然与强制循环回路水动力特性分析 [D]. 上海: 上海交通大学, 2012. |
[4] | [3]毕勤成, 刘伟民, 高峰, 等. U型管高压汽?惨毫较嗔鞫?密度波型不稳定性的实验研究 [J]. 核动力工程, 2005, 26(6): 564??567. |
[5] | BI Qincheng, LIU Weimin, GAO Feng, et al. Experiment study on density??wave instability of high pressure steam??water two??phase flow in U??type tube [J]. Nuclear Power Engineering, 2005, 26(6): 564??567. |
[6] | [5]AMBROSINI W. On the analogies in the dynamic behaviour of heated channels with boiling and supercritical fluids [J]. Nuclear Engineering and Design, 2007, 237(11): 1164??1174. |
[7] | [6]CHATOORGOON V. Stability of supercritical fluid flow in a single??channel natural??convection loop [J]. International Journal of Heat and Mass Transfer, 2001, 44(10): 1963??1972. |
[8] | [7]XIONG T, YAN X, HUANG S F, et al. Modeling and analysis of supercritical flow instability in parallel channels [J]. International Journal of Heat and Mass Transfer, 2013, 57(2): 549??557. |
[9] | [8]薛爱军, 程旭. 超临界水热力系统的稳定性的简化模型分析 [J]. 核动力工程, 2009, 30(5): 35??39. |
[10] | XUE Aijun, CHENG Xu. Stability analysis of a simplified model of supercritical water??cooled system [J]. Nuclear Power Engineering, 2009, 30(5): 35??39. |
[11] | [9]ORTEGA G T, CLASS A, LAHEY R T, et al. Stability analysis of a uniformly heated channel with supercritical water [J]. Nuclear Engineering and Design, 2008, 238(8): 1930??1939. |
[12] | [10]张伟强, 李会雄, 张庆, 等. 内螺纹管内超临界水的流动阻力特性试验研究 [J]. 中国电机工程学报, 2013, 33(7): 1??7. |
[13] | ZHANG Weiqiang, LI Huixiong, ZHANG Qing, et al. Experimental study on flow resistance of supercritical pressure water in an internally ribbed tube [J]. Proceedings of the CSEE, 2013, 33(7): 1??7. |
[14] | [11]潘杰, 杨冬, 肖荣鸽. 低质量流速优化内螺纹管摩擦阻力特性实验研究 [J]. 高技术通讯, 2014, 24(4): 429??423. |
[15] | [2]黄可欣, 高峰, 毕勤成, 等. 超临界锅炉并联倾斜管内螺纹管两相流密度波型脉动数值研究 [J]. 核动力工程, 2008, 29(4): 63??69. |
[16] | HUANG Kexin, GAO Feng, BI Qincheng, et al. Numerical research on density wave oscillation of two??phase flow in parallel inclined internally ribbed pipes for supercritical pressure boiler [J]. Nuclear Power Engineering, 2008, 29(4): 63??69. |
[17] | [4]冯建, 田文喜, 巫英伟, 等. 超临界水并联通道流动不稳定性理论研究 [J]. 原子能科学技术, 2012, 46(4): 404??409. |
[18] | FENG Jian, TIAN Wenxi, WU Yingwei, et al. Theoretical study on flow instability of supercritical water in parallel channels [J]. Atomic Energy Science and Technology, 2012, 46(4): 404??409. |
[19] | PAN Jie, YANG Dong, XIAO Rongge. Experimental investigation on frictional resistance characteristics of optimized rifled tube at low mass flux [J]. Chinese High Technology Letters, 2014, 24(4): 429??423. |
[20] | [12]陶文铨. 数值传热学 [M]. 2版. 西安: 西安交通大学出版社, 2011: 140??141. |