期刊文献+

压水堆冷却剂中硼酸浓度对核主泵性能影响研究 被引量:17

Effect of Boric Acid Concentration on Reactor Coolant Pump Performance in PWRs
下载PDF
导出
摘要 采用Fluent软件对混流式核主泵叶轮在多流量工况和冷却剂中含有不同浓度硼酸溶液的多方案进行三维湍流流动数值模拟,结合实验数据,分析了清水与硼酸溶液对核主泵性能影响的差异,着重研究了硼酸浓度对叶轮的影响程度,并对采用数值计算方法预测核主泵中以清水作为模拟介质的可行性进行了分析。结果表明,即使在极限硼酸浓度下,冷却介质中硼酸浓度亦对核主泵性能影响较小。由此验证了采用清水作为模拟介质是可行的。 Using the computational fluid dynamics software Fluent,the three-dimensional turbulent flow of the reactor coolant pump(RCP) impeller at different flow rates and different concentrations of boric acid is simulated.With the experimental data,different effects on RCP performance are analyzed between water and boric acid,especially the influence to the impeller.The feasibility of taking the water as coolant in RCP by using numerical simulation method is analyzed,and the result shows that negligible differences in water and boric acid was acquired even in abnormal concentration of boric acid.It proved that the using of water as coolant when conducting a simulation is feasible.
出处 《核动力工程》 EI CAS CSCD 北大核心 2011年第4期95-98,117,共5页 Nuclear Power Engineering
基金 973国家重点基础研究资助项目(2009CB724303)
关键词 硼酸 核主泵 性能影响 数值模拟 Boric acid Reactor coolant pump Performance influence Numerical simulation
  • 相关文献

参考文献7

  • 1Pastina B,Isabey J,Hickel B.The Influence of water Chemistry on the Radiolysis of the Primary Coolant Water in Pressurized Water Reactors[J].Journal of Nuclear Materials,1999,264(3):309-318.
  • 2樊均福 方惠君 储可云 等.动水腐蚀回路中硼和锂的浓度控制.核动力工程,1982,:18-22.
  • 3Hohne T,Kliem S,Rohde U,et al.Boron Dilution Transients during Natural Circulation Flow in PWR-Experiments and CFD Simulations[J].Nuclear Engineering and Design,2008,238(8):1987-1995.
  • 4Reeder D L.Boric acid Effects on Water Properties and LOCA Thermal-hydraulics in PWRs[R].LTR-20-91,British Library,1979.
  • 5王春林,彭娜,康灿,赵佰通,张浩.模型泵内部流场的数值模拟[J].核动力工程,2009,30(4):81-85. 被引量:12
  • 6袁丹青,陈向阳,杨敏官,袁寿其.基于CFX的国内某300MWe级核电站主泵内部流场数值研究[J].流体机械,2009,37(8):17-20. 被引量:2
  • 7李世煌.叶片泵的非工况及其优化设计[M].北京:机械工业出版社,2005.

二级参考文献13

  • 1王勤湖,李社坤,卢文跃,于海峰,曹智鹏.压水堆核电站一回路工况变化对主泵主要机械性能的影响[J].核动力工程,2005,26(S1):103-108. 被引量:24
  • 2施法佳,陈红勋.轴流泵内部流动数值模拟中湍流模式可用性的研究[J].上海大学学报(自然科学版),2006,12(3):273-277. 被引量:13
  • 3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
  • 4Andreas Poullikkas. Effects of Two-phase Liquid-Gas Flow on the Performance of Nuclear Reactor Cooling Pumps[J]. Progress in Nuclear Energy, 2003, 42(1): 3-10.
  • 5Jose Caridad, Frank Kenyery. CFD Analysis of Electric Submersible Pumps (ESP) Handling Two-Phase Mixtures[J]. Transaction of the ASME: Journal of Energy Resource Technology, 2004, 126 (2): 99-102.
  • 6Eisele K, Zhang Z, Casey M V, et al. Flow Analysis in a Pump Diffuser-Part 1: LDA and PTV Measurements of the Unsteady Flow[J]. ASME Journal of Fluid Engi- neering, 1997, 119 (12): 968-977.
  • 7ROHDE U, HOHNE T, KLIEM S, et al. Fluid mixing and flow distribution in a primary circuit of a nuclear pressurized water reactor--Validation of CFD codes [J]. Nuclear Engineering and Design, 2007, 237: 1639 - 1655.
  • 8DURMUS KAYA. Experimental study on regaining the tangential velocity energy of axial flow pump [ J ]. Energy Conversion and Management, 2003, 44: 1817- 1829.
  • 9UZOL O, BRZOZOWSKI D,CHOW Y C,et al. A database of PIV measurements within a turbomachinery stage andsample comparisons with unsteady RANS[ J]. Journal of Turbulence, 2007.
  • 10Shao-Yi Hsia, Shih-Ming Chiu and Jyin-Wen Cheng. Sound field analysis and simulation for fluid machines [ J ]. Advances in Engineering Software, 2008.

共引文献12

同被引文献128

引证文献17

二级引证文献85

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