Application of two preconditioned generalized conjugate gradient methods to three-dimensional neutron and photon transport equations

被引:5
作者
Chen, GS [1 ]
Sheu, RD [1 ]
机构
[1] Natl Tsing Hua Univ, Dept Engn & Syst Sci, Nucl Engn Program, Hsinchu 30043, Taiwan
关键词
TORT; neutron transport; CGS; Bi-CGSTAB; preconditioner;
D O I
10.1016/j.pnucene.2004.08.003
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In this paper the preconditioned generalized conjugate gradient methods are applied to solve the linear system of equations that arise in three-dimensional neutron and photon transport equations. These generalized conjugate gradient methods are the CGS (conjugate gradient square) algorithm and the Bi-CGSTAB (bi-conjugate gradient stabilized) algorithm. Several subroutines are developed from these preconditioned generalized conjugate gradient methods for use in time-independent multi-group three-dimensional neutron and photon transport equations. These subroutines are connected to the computer program TORT. The reason for choosing the preconditioned generalized conjugate gradient methods is that these methods have good residual error control procedures during computation and have good convergence rates. We test a problem having an 8 set of matrix equations with 24255 unknowns each, in a personal computer with an AMD Athlon-XP1600+ central processing unit (CPU) and using Mandrake Linux 6.3 as the operating system. The point-wise incomplete LU factorization (ILU) and modified point-wise incomplete LU factorization (MILU) are the preconditioning techniques used in the test problem. We find that the preconditioned CGS and Bi-CGSTAB methods with the preconditioner ILU are more efficient than with the preconditioner MILU in the test problem. The numerical solution of flux by the preconditioned Bi-CGSTAB and CGS methods produces the same results as those obtained by the successive over relaxation method (SOR) in the TORT program which is usually used for the calculation of radiation shielding in nuclear power plant and nuclear spent fuel storage. (C) 2004 Published by Elsevier Ltd.
引用
收藏
页码:11 / 23
页数:13
相关论文
共 21 条
[11]   3D radiation transport benchmark problems and results for simple geometries with void region [J].
Kobayashi, K ;
Sugimura, N ;
Nagaya, Y .
PROGRESS IN NUCLEAR ENERGY, 2001, 39 (02) :119-144
[12]   Tort solutions with FNSUNCL3 for Kobayashi's 3D benchmarks [J].
Konno, C .
PROGRESS IN NUCLEAR ENERGY, 2001, 39 (02) :167-179
[13]  
Ortega J, 1988, Introduction to Parallel and Vector Solution of Linear Systems
[14]   RADIATION EXPOSURE INSIDE REINFORCED-CONCRETE BUILDINGS AT NAGASAKI [J].
RHOADES, WA ;
CHILDS, RL ;
INGERSOLL, DT .
HEALTH PHYSICS, 1992, 63 (05) :510-521
[15]  
RHOADES WA, 1995, TORT VERSION 3 3 DIM
[16]   BILUM: Block versions of multielimination and multilevel ILU preconditioner for general sparse linear systems [J].
Saad, Y ;
Zhang, J .
SIAM JOURNAL ON SCIENTIFIC COMPUTING, 1999, 20 (06) :2103-2121
[17]  
SAAD Y, 1996, ITERATIVE METHOD SPA
[18]   CGS, A FAST LANCZOS-TYPE SOLVER FOR NONSYMMETRIC LINEAR-SYSTEMS [J].
SONNEVELD, P .
SIAM JOURNAL ON SCIENTIFIC AND STATISTICAL COMPUTING, 1989, 10 (01) :36-52
[19]   CONJUGATE-GRADIENT LIKE METHODS AND THEIR APPLICATION TO EIGENVALUE PROBLEMS FOR NEUTRON DIFFUSION EQUATION [J].
SUETOMI, E ;
SEKIMOTO, H .
ANNALS OF NUCLEAR ENERGY, 1991, 18 (04) :205-227
[20]   BI-CGSTAB - A FAST AND SMOOTHLY CONVERGING VARIANT OF BI-CG FOR THE SOLUTION OF NONSYMMETRIC LINEAR-SYSTEMS [J].
VANDERVORST, HA .
SIAM JOURNAL ON SCIENTIFIC AND STATISTICAL COMPUTING, 1992, 13 (02) :631-644