A NEW NODAL S(N) TRANSPORT METHOD FOR 3-DIMENSIONAL HEXAGONAL GEOMETRY

被引：26

作者：

IKEDA, H ^{[1
]}

TAKEDA, T ^{[1
]}

机构：

[1] OSAKA UNIV, FAC ENGN, DEPT NUCL ENGN, SUITA, OSAKA 565, JAPAN

来源：

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 1994年 / 31卷 / 06期

关键词：

TRANSPORT CALCULATIONS; ACCURACY; ERRORS; NODAL S(N) METHOD; ANALYTIC INTRA-NODE FLUX DISTRIBUTION; DISCONTINUITY; TRANSVERSE-LEAKAGE; NODAL-EQUIVALENT FINITE DIFFERENCE ALGORITHM; STABILIZATION; ITERATIVE CONVERGENCE; 3-DIMENSIONAL HEXAGONAL GEOMETRY; FAST REACTORS; KEFF; FLUX; NEUTRON SOURCES; SPATIAL DISTRIBUTION;

D O I：

10.3327/jnst.31.497

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：

A new nodal S(N) transport method has been developed so as to perform accurate transport calculation.s in three-dimensional (3-D) hexagonal geometry. In the present method the neutron angular distributions of intra-node fluxes and transverse-leakage are represented using the S(N) quadrature set, and the spatial distribution of neutron source is approximated by a quadratic polynomial expansion. Additionally, the authors have applied the nodal-equivalent finite difference algorithm to 3-D hexagonal geometry in order to establish a stable and efficient iterative scheme. The present method has been applied to a fast reactor benchmark problem. The results of the present method agree well with those of a Monte Carlo method, the difference in k(eff) being less thin 0.05%DELTAk. This shows high accuracy of the present method.

引用

页码：497 / 509

页数：13

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