期刊文献+

基于特征线方法的三维中子输运程序(Ⅱ)——数值验证 被引量:5

Three Dimension Neutron Transport Characteristics Method Code(Ⅱ)——Numerical Verification
在线阅读 下载PDF
导出
摘要 介绍了开发的三维中子输运特征线方法程序TCM,使用数值实例对TCM的准确性进行了验证,同时比较了不同插值阶数、离散角度数目和网格大小对计算结果的影响。结果表明,三维特征线方法程序TCM能够求解任意几何形状及反射边界条件的中子输运问题,计算结果具有较高的精度。 Three dimensional characteristics method code TCM is introduced and verified in this paper.And the influence of boundary interpolation,quadrature set and mesh size on accuracy of results are given.It is shown that TCM,using interpolation treatment of boundary condition,can calculate the neutron transport problems accurately,of which geometry and reflective boundary are arbitrary.
出处 《核动力工程》 EI CAS CSCD 北大核心 2010年第2期16-20,共5页 Nuclear Power Engineering
关键词 输运方程 特征线方法 反射边界条件 插值 基准题 Neutron transport equation Method of characteristics Reflective boundary condition Interpolation Benchmark
  • 相关文献

参考文献6

二级参考文献10

  • 1Halsall M J.CACTUS:A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries[R].AEEW-R 1291.1988.
  • 2Knott D.KRAM:A Lattice Physics Code for Modeling the BWR Fuel Designs[D].Doctoral Thesis,USA:Pennsylvania State University,1990.
  • 3Jevremovic T,Vujic J,Tsuda K.ANEMONA-A Neutron Transport Code for General Geometry Reactor Assemblies Based on the Method of Characteristics and R-Function Solid Modeler[J].Annals of Nuclear Energy,2001,28 (2):125-152.
  • 4Suslov I.Improvement in the Long Characteristics Method and Their Efficiency for Deep Penetration Calculations[J].Progress in Nuclear Energy,2001,39 (2):233-243.
  • 5Wu G J,Roy R.A New Characteristics Algorithm for 3D Transport Calculations[J].Annals of Nuclear Energy,2003,30 (1):1-16.
  • 6Sanchez R,Li M,Santandrea S.Treatment of Boundary Conditions in Trajectory-Based Deterministic Transport Methods[J].Nuclear Science and Engineering,2002,140:23-50.
  • 7Emmett M B.MORSE-CGA,A Monte Carlo Radiation Transport Code with Array Geometry Capability[R].0RNL-6174.America:ORNL,1985.
  • 8Stepanek J.Calculation of Four Thermal Reactor Benchmark Problems[R].EIR-464,America:ANS,1982.
  • 9Gehin J C.PWR Lattic Benchmark Problems[R].Ad Hoc Committee on Reactor Benchmarks,America:ANS,Reactor Physics Division,1996,1290-1310.
  • 10邓力.多群中子散射角分布L阶截断出负的改进[J].原子能科学技术,2003,37(5):405-410. 被引量:2

共引文献18

同被引文献33

  • 1PETKOV P T, TAKEDA T. Transport Calculations of MOX and UO2 Pin Cells by the Method of Characteristics [J]. Journal of Nuclear Science and Technology, 1998, 35 (12): 874-885.
  • 2Santandrea S, Sanchez R. Positive Linear and Nonlinear Surface Characteristic Schemes for the Neutron Transport Equation in Unstructured Geometries [C]. Proc. Int. Conf. on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002, Seoul, October 7-10, 2002.
  • 3Tellier Romain Le, Hebert Alain. On the Integration Scheme along a Trajectory for the Characteristics Method[J]. Annals of Nuclear Energy, 2006, 33: 1260-1269.
  • 4OECD. Benchmark on Deterministic Transport Caleultions Without Spatial Homogenisation-A 2-D/3-D MOX Fuel Assembly Benchmark[R]. Nuclear Science NEA/ NSC/DOC (2003) 16, 2003.
  • 5Smith M A, Palmiotti G, Taiwo T A, et al. Benchmark Specification for Deterministic MOX Fuel Assembly Transport Calculations without Spatial Homogenisation (3-D extension C507 MOX) [R]. NEA/NSC/DOC (2001) 4, 2001.
  • 6Takeda T, Ikeda H. 3-D Neutron Transport Bencmarks[R]. Technical Report OECD/NEA Committee on Reactor Physics (NEACRP), 1991.
  • 7Sanchez R,Chetaine A.A synthetic acceleration for a two-dimensional characteristic method in unstructured meshes[J].Nucl Sci Eng,2000,136:122-139.
  • 8Michael R Zika,Marvin L Adams.Transport synthetic acceleration for long-characteristics assembly-level transport problems[J].Nucl Sci Eng,2000,134:135-158.
  • 9Wu G J,Boy R.A new characteristics algorithm for 3D transport calculations[J].Ann Nucl Energy,2003,30(1):1-16.
  • 10Han Gyu Joo,Jin Young Cho,Ha Yong Kim,et al.Dynamic implementation of the equivalence theory in the heterogeneous whole core transport calculation[C] //Physor 2002,Seoul,Korea,Session 13A-02.2002.

引证文献5

二级引证文献10

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