期刊文献+

喷动床反应器内流体动力特性的数值模拟 被引量:2

Hydrodynamic Simulation of Fluid in Spouted Bed Reactor
下载PDF
导出
摘要 采用欧拉-欧拉双流体模型,颗粒动理学理论模拟颗粒相流动,对喷动床核反应器内的流体动力行为进行了数值模拟。模拟得到了喷动床核反应器内颗粒浓度标准方差、空隙率和颗粒速度分布。研究结果表明喷动床核反应器内颗粒浓度标准方差先逐渐增大至最大值后下降。分析了摩擦应力模型和倒锥体角度等影响因素对喷动床核反应器内的流体动力特性的影响。 Hydrodynamics of fluid was numerically studied by means of an Eulerian-Eulerian two-fluid model in a spouted bed reactor.Nuclear fuel particles collisions were modeled by the kinetic theory of granular flow.The distribution of standard variance of particle concentration,porosity and velocity were obtained in the nuclear reactor.Numerical results indicate that the value of the standard variance of particle concentration firstly increased with the increasing mean particle concentration and after that decreased gradually.The influences of the frictional stresses and inclined angles on flow behavior were analyzed.
出处 《节能技术》 CAS 2011年第1期35-41,共7页 Energy Conservation Technology
基金 国家自然科学基金资助项目(50806019)
关键词 喷动床核反应器 双流体模型 数值模拟 spouted bed nuclear reactor two-fluid model numerical simulation
  • 相关文献

参考文献7

二级参考文献8

共引文献65

同被引文献23

  • 1孙巧群,高建民,朱卫兵,陆慧林.流化床反应器内气固两相流动特性的研究[J].热能动力工程,2010,25(6):621-626. 被引量:3
  • 2MOLERUS O, BURSCHKA A, DIETZ S, et al. Particle migration at solid surfaces and heat transfer in bubbling fluidized beds: particle migration measurement systems [ J ]. Chemical Engineering Science, 1995, 50 (5) : 871 - 877.
  • 3MOLERUS O, BURSCHKA A, DIETZ S, et al. Particle migration at solid surfaces and heat transfer in bubbling fluidized beds: prediction of heat transfer in bubbling fluidized beds [ J ]. Chemical Engineering Science, 1995, 50(5) : 879 -885.
  • 4WANG S Y, LI X, LU H L, et al. Simulations of flow behavior of fuel particles in a conceptual helium-cooled spout fluidized bed nuclear reactor [ J ]. Nuclear Engineering and Design, 2009, 239( 1 ) : 106 - 115.
  • 5LATHOUWERS A, AGUNG A. Dynamics modeling and stability analysis of a fluidized bed nuclear reactor [ J ]. Progress in Nuclear Energy, 2003, 43 (1/2/3/4): 437 - 443.
  • 6SEFIDVASH F. Status of the small modular fluidized bed light water nuclear reactor concept [ J ]. Nuclear Engineering and Design, 1996, 167 (2/3) : 203 - 214.
  • 7DE OLIVEIRA C R. An arbitrary geometry finite element method for multigroup neutron transport with anisotropic[J~. Progress in Nuclear Energy, 1986, 18 (1/2) : 227 -236.
  • 8PAIN C C, DE OLIVEIRA C R, GODDARD A J H, et al. Non-linear space-dependent kinetics for criticality assessment of fissile solutions [ J ]. Progress in Nuclear Energy, 2001, 39 ( 1 ) : 53 - 114.
  • 9PAIN C C, GOMES J L, EATON M D, et al. Space- dependent kinetics simulation of a gas-cooled fluidized bed nuclear reactor [ J ]. Nuclear Engineering and Design, 2002, 219(3) : 225 -245.
  • 10GOMES J L, PAIN C C, EATON M D, et al. Investigation of nuclear criticality within a powder using coupled neutronics and thermofluids [ J ]. Annals of Nuclear Energy, 2008, 35 ( 11 ) : 2073 - 2092.

引证文献2

二级引证文献1

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