期刊文献+

非线性迭代半解析节块方法在压水堆燃料管理计算中的应用 被引量:7

Application of Nonlinear Iteration Semi-analytical Nodal Method in the PWR Fuel Management Calculation
在线阅读 下载PDF
导出
摘要 利用半解析节块法的非线性迭代计算方法求解多维多群中子扩散方程。数值结果表明 ,这种非线性迭代半解析节块法具有较高的精度 ,并且在计算效率上比传统方法有很大的提高。将这种方法应用于SIMULATE E中 ,研制了压水堆燃料管理计算程序CSIM 3B ,对秦山核电厂第一循环进行了跟踪校核计算 。 The semi-analytical nodal method with the nonlinear iteration procedure is used for solving the multi-group multi-dimensional neutron diffusion equation.Numerical results show that this method has comparablly high accuracy and improves considerably computational efficiency compared to the conventional nodal methods.The method is embedded into the SIMULATE-E.As a result the code CSIM-3B is developed for PWR fuel management calculation.Following the actual operation history,Qinshan Nuclear Power Plant cycle 1 is calculated using CSIM-3B.The calculated results conform well with the measured value.
出处 《核科学与工程》 CAS CSCD 北大核心 2003年第1期14-19,共6页 Nuclear Science and Engineering
关键词 半解析节块方法 压水堆 计算 非线性迭代 燃料管理 CSIM-3B程序 nonlinear iteration nodal method fuel management
  • 相关文献

参考文献12

  • 1[1]Lawrence R. D.,Progress in Nodal Methods for the Solution of the Diffusion and Transport Equations.Progress in Nuclear Energy,1986,17(3):271~301
  • 2[2]Finnemann H., Bennewitz F.,et al., Interface Current Techniques for Multidimensional Reactor Calculations,Atomkernenergie, 1977,30:123~128
  • 3[3]Lawrence R.D., A Nodal Green's Function Method for Multidimensional Neutron Diffusion Calculations. PH.D.thesis,University of Illinois,1979
  • 4[4]Smith K. S., An Analytic Nodal Method for Solving the Two Group Multidimensional Static and Transient Neutron Diffusion Equation.Thesis,Department of Nuclear Engineering,Massachusetts Institute of Technology,1979
  • 5[5]Smith K.S.,Nodal Method Strategy Reduction by Nonlinear Iteration.Tran.Am.Nucl.Soc.,1983,44:265~266
  • 6[8]Turinsky P.J., Al-chalabi M.K., etc., NESTLE:A Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue,Adjoint,Fixed-Source Steady-state and Transient Problems.EGG-NRE-11406,June,1994
  • 7[9]Smith K.S., Assembly Homogenization Techniques for Light Water Reactor Analysis.Progress in Nuclear Energy,1986,17(3):303~335
  • 8[10]Zimin V.G., Ninokata H., Nodal Neutron Kinetics Model Based on Nonlinear Iteration Procedure for LWR Analysis.Ann. Nucl.Energy,1998,25(8):507~528
  • 9[11]Zimin V.G., Ninokata H., et al., Polynomial and Semi-Analytic Nodal Methods for Nonlinear Iteration Procedure.Nucl.Tech.,1997,120:994~1002
  • 10[12]Bandini B.R.,A Three-Dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal hydraulic Computer Code.PH.D.Thesis,Pennsylsvansia State University,1990

同被引文献16

  • 1Esser P D, Smith K S. A semianalytic two-group nodal model for SIMULATE-3[J]. Trans Am Nucl Soc, 1993,68:220-222.
  • 2Rempe K R, Smith K S. SIMUI.ATE-3 Pin Power Reconstruction: Methodology and Benchmarking[J]. Nuclear Science and Engineering, 1989, 103-334.
  • 3Jae Man Noh , Nam Zin Cho. A New Approach of Analytic Basis Function Expansion to Neutron Diffusion Nodal Calcution[J]. Nuclear Science and Engineering, 1994, 116: 165-180.
  • 4Han-Gyu Joo, private communication[R].
  • 5Benchmark Problem Book, ANL-7416[J]. Argonne National Laboratory, 1977, 2(Suppl).
  • 6Jae Man Noh , Nam Zin Cho. A Multigroup Diffusion Nodal Scheme in Rectangular and Hexagonal Geometries [P]: Hybrid of AFEN and PEN Methods, PHYSOR96.
  • 7Benchmark on Deterministic Transport Calculations Without Spatial Homogenisation [M]//MOX Fuel Assembly 3 D Extension Case: ISBN 92 64 01069-6. NEA/NSC/DOC(2005) 16.
  • 8丁小川,路海晋,赵强.基于ADI的一种堆芯物理实时仿真算法[J].核动力工程,2011,32(3):130-133. 被引量:1
  • 9竹生东,谢仲生.燃料组件内精细功率的重构[J].西安交通大学学报,2000,34(5):32-36. 被引量:10
  • 10竹生东,谢仲生.非线性迭代方法在中子扩散计算中的应用[J].核动力工程,2000,21(3):259-263. 被引量:4

引证文献7

二级引证文献14

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