期刊文献+

1000MW级核主泵压水室出口压力脉动 被引量:16

Collector discharge pressure fluctuation of 1 000 MW nuclear reactor coolant pump
下载PDF
导出
摘要 为了研究压力脉动在核主泵压水室出口处的变化规律及其影响因素,以国内某1 000 MW核电站主泵为研究对象,应用计算流体动力学软件Fluent进行定常与非定常三维数值模拟,得到压水室内部流场特性及计算点的压力脉动情况,并对其进行时域和频域分析.结果表明:回流是引起压水室与出口交接处压力脉动的原因之一;在不同工况下压水室出口及其前后区域内存在明显的压力脉动,偏离额定工况越大,压力脉动波动幅度越大;压水室出口及其前后区域内,上侧的脉动幅度比下侧小,上侧的平均脉动幅度CA在0.9Q时为11.15%,在1.0Q时为9.62%,在1.2Q时为13.78%,下侧的平均脉动幅度,在0.9Q时为13.62%,在1.0Q时为12.53%,在1.2Q时为15.79%;靠近导叶出口处,泵壳两侧处的脉动幅度要大于靠近出口轴线附近的脉动幅度,远离导叶出口处,泵壳内的脉动幅度从上侧到下侧,逐渐递增;在额定工况时转频是各监测点压力脉动的主要影响因素,在小流量和大流量时转频和叶频是各监测点压力脉动的主要影响因素. To investigate the collector discharge pressure fluctuation characteristics and the related fac- tors in a 1 000 MW nuclear reactor coolant pump, steady and unsteady 3-dimensional numerical simu- lation was conducted to depict the inner flow inherence and detailed pressure content of a domestic pump model. Both time and frequency domain analysis were further put forward. It is shown that re- verse flow is one of the reasons that cause the pressure fluctuations at the joint of the collector and the discharge. Obvious pressure fluctuations exit at the collector discharge and the adjacent area. In addi- tion, the more the operation condition deviates from the design point, the more severe the pressure fluctuations are. The fluctuation amplitude in the upper passage is higher than that in the lower pas- sage. The mean amplitude are 11.5% , 9.62% and 13.78% respectively in the upper passage, while they are 13.62%, 12.53% and 15.79% respectively in the lower one under the flow rates of 0.9Q, 1.0Q, and 1.2Q. At the adjacent diffuser vanes, the fluctuation amplitude near both sides of the ca- sing wall is larger than that near the mid-span line. In the regions far from the diffuser outlet, the fluc- tuation amplitude is increased gradually from the top side wall of casing to the bottom one. The shaft rotating frequency is the major factor influencing pressure fluctuation at ever monitor point when the pump is working at the design point. However, both the shaft rotating frequency and the blade passing frequency are the main factors when it works at off-design points.
出处 《排灌机械工程学报》 EI 北大核心 2012年第4期395-400,共6页 Journal of Drainage and Irrigation Machinery Engineering
基金 国家杰出青年科学基金资助项目(50825902) 江苏省自然科学基金资助项目(BK2011504) 江苏高校优势学科建设工程项目
关键词 核主泵 压水室出口 压力脉动 数值模拟 时域分析 频域分析 nuclear reactor coolant pump discharge chamber outlet pressure fluctuation numerical simulation time-domain analysis frequency-domain analysis
  • 相关文献

参考文献10

  • 1Rzentkowski G, Zbroja S. Acoustic characterization of a CANDU primary heat transport pump at the blade-pas- sing frequency[ Jl. Nuclear Engineering Design, 2000, 196(1) : 63 -68.
  • 2In Soo Koo, Whan Woo Kim. The development of reac- tor coolant pump vibration monitoring and a diagnostic system in the nuclear power plant [ J]. ISA Transac- tions, 2000,39(3) : 309 -316.
  • 3. Kazem Farhadi, Anis Bousbia-salah, Franseeso D Auria. A model for the analysis of pump start-up transients in Tehran research reactor [ J ]. Progress in Nuclear Ener- gy, 2007, 49(7) :499 -510.
  • 4Martin W Trethewey, Joshua C Friell. A spectral simu- lation approach to evaluate probabilistic measurement precision of a reactor coolant pmnp torsional vibration shaft crack monitoring system[ J]. Journal of Sound and Vibration, 2008, 310(4/5 ) : 1036 - 1056.
  • 5马辉,周文建,闻邦椿.核电站反应堆冷却剂泵的模态分析[J].机械制造,2006,44(10):14-17. 被引量:10
  • 6陈向阳,袁丹青,杨敏官,袁寿其.300MW级核电站主泵压力脉动研究[J].核动力工程,2010,31(3):78-82. 被引量:10
  • 7Muggli F A. CFD calculation of a mixed flow pump characteristic from shut-off to maximum flow E C //Pro- ceedings of the ASME Fluids Engineering Division Sum- mer Meeting,2003:249 - 254.
  • 8Untaroiu A, Throckmorton A L, Patel S M, eta]. Nu- merical and experimental analysis of an axial flow left ventrieular assist device:The influence of the diffuser on overall pump performance [ J ]. Artificial Organs, 2005, 29(7) :581 -591.
  • 9唐宏芬,张梁,吴玉林.双级轴流泵内部三维紊动流场CFD分析[J].工程热物理学报,2003,24(3):423-425. 被引量:27
  • 10李颖,周文霞,张继革,王德忠.核反应堆冷却剂循环泵全流道三维数值模拟及性能预估[J].原子能科学技术,2009,43(10):898-902. 被引量:12

二级参考文献22

  • 1宋雪萍,张积存,闻邦椿.汽轮发电机组轴系扭振特性分析[J].机械制造,2005,43(7):11-13. 被引量:2
  • 2王福军.CFD在水力机械湍流分析与性能预测中的应用[J].中国农业大学学报,2005,10(4):75-80. 被引量:54
  • 3周文建,陈宏,闻邦椿.核电站反应堆冷却剂泵的地震响应分析[J].振动与冲击,2006,25(1):32-35. 被引量:19
  • 4吴玉林,韩海,曹树良.水轮机转轮内全三维紊流计算及效率预估[J].工程热物理学报,1996,17(3):313-316. 被引量:16
  • 5秦武,李志鹏,沈宗沼,靳卫华.核反应堆冷却剂循环泵的现状及发展[J].水泵技术,2007(3):1-6. 被引量:35
  • 6LIEN F S, LESCHZINER A. Assessment of turbulent transport models including nonlinear RNG eddy viscosity formulation and second moment closure for flow over backward facing step[J]. Computers and Fluids, 1994, 23(8): 983-1 004.
  • 7SIERRA F Z, MAZUR Z, KUBIAK J, et al. Modeling of the flow at the last stage blade tenon in a geothemal turbine using renorm alization group theory turbulence model[J]. Applied Thermal Engineering, 2000, 20: 81-101.
  • 8REN Jing, CAO Shuliang, WU Yulin. Numerical simulation of the three-dimensional turbulent flow in an axial flow runner[C] /// Proceeding of 3^rd ASME/JSME Joint Fluids Engineering Division Summer Meeting. San Francisco: CA, 1999: 369-382.
  • 9Rzentkowski G, Zbroja S. Acoustic Characterization of a CANDU Primary Heat Transport Pump at the BladePassing Frequency[J]. Nuclear Engineering Design, 2000, 196: 63-68.
  • 10Runkel J, Stegemann D, Vortriede A. Operating Experience with an On-Line Vibration Control System for PWR Main Coolant Pumps[J]. Nuclear Engineering Design, 1998, 183: 157-167.

共引文献53

同被引文献208

引证文献16

二级引证文献118

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部