期刊文献+

基于CAD建模和有限元方法的三维中子扩散程序 被引量:4

3-D neutron diffusion code based on CAD preprocessing and the finite element method
原文传递
导出
摘要 有限元方法(finite element method,FEM)适应于复杂几何问题的数值计算,但目前反应堆物理有限元程序所采用的前处理(即几何建模和网格划分)方法繁琐抽象,较难应用于高维复杂结构。该文通过采用计算机辅助设计(computer aided design,CAD)商业软件GAMBIT进行可视化自动建模和网格划分,并应用于自主开发的有限元三维中子扩散程序FEMND,实现了对高维复杂堆芯的直接准确模拟。该程序系统对二维和三维几何分别采用非结构三角形和四面体网格划分,采用不完全LU分解预优共轭梯度法求解代数方程组,可处理临界和含外源问题。通过多个理论模型和基准问题验证了程序的可靠性和正确性,表明有限元方法与CAD前处理相结合,可以充分发挥有限元方法的优势,实现对复杂结构堆芯的有效模拟。 The finite element method (FEM) has advantages for analyzing complex geometry; however, the preprocessing used in finite element codes for nuclear reactor physics is tedious, complicated and not convenient for high dimensional cases. This paper describes an automatical modeling and meshing method using a graphical interface based on the commercial computer aided design (CAD) software GAMBIT. The system is used in a three-dimensional neutron diffusion code, FEMND, to simulate complex reactor cores. This code uses unstructured triangular and tetrahedral elements for two and three dimensional problems, with the incomplete I.U factorized conjugate gradient (ILUCG) algorithm used to solve the algebraic equations. Both critical and external source driven problems can be simulated. The code has been verified with several benchmarks. This code combines the finite element
出处 《清华大学学报(自然科学版)》 EI CAS CSCD 北大核心 2012年第7期901-905,共5页 Journal of Tsinghua University(Science and Technology)
基金 国家磁约束核聚变能研究专项(2010GB111002)
关键词 中子扩散 有限元方法 CAD 非结构网格 预优共轭梯度法 neutron diffusion finite element method computer aided design (CAD) unstruclured mesh preconditioned conjugate gradient method
  • 相关文献

参考文献9

  • 1顾丽珍,王永庆,于素花,等.有限元法在计算二维反应堆中子扩散方程中的应用EJ].清华大学学报,1980,20(4):97-110.
  • 2吴宏春,谢仲生.两维快堆中子扩散方程的有限元逼近[J].核动力工程,1992,13(6):26-31. 被引量:6
  • 3陈昌友.有限元方法在二维六角形组件堆芯临界问题计算中的应用[J].计算物理,1997,14(4):569-571. 被引量:2
  • 4Lucas D S, Gougar H D, Wareing T, et al. Comparison of the 3 D Deterministic Neutron Transport Code Attila to Measure Data, MCNP and MCNPX for the Advanced Test Reactor [R]. INL/CON 05 00662, 2005.
  • 5Ise T, Yamazaki T, Nakahara Y. Application of the finite element method to the three dimensional neutron diffusion equation [C]// NEACRP 21st Meeting. Tokai, 1978.
  • 6GAMBIT 2.2 Tutorial Guide [M]. Fluent Inc, 2004.
  • 7Argonne (;ode Center. Benchmark Problem Book [R]. ANL 7416 Supplement 2, 1977.
  • 8Christensen B. Three Dimendonal Static and Dynamic Reactor Calculations by the Nodal Expansion Method [R]. Riso-R-496, 1985.
  • 9Soon S K, Bruce G S. Validation of Improved 3D ATR Model [R]. INL/CON 05 00322, 2005.

二级参考文献1

  • 1吴宏春,有限元方法在快堆临界问题计算中的应用,1991年

共引文献5

同被引文献26

引证文献4

二级引证文献4

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