FINITE-ELEMENT METHOD FOR NEUTRON-TRANSPORT .2. SOME PRACTICAL CONSIDERATIONS

被引：17

作者：

GALLIARA, J ^{[1
]}

WILLIAMS, MMR ^{[1
]}

机构：

[1] UNIV LONDON QUEEN MARY COLL,DEPT NUCL ENGN,LONDON E1 4NS,ENGLAND

来源：

ANNALS OF NUCLEAR ENERGY | 1979年 / 6卷 / 04期

关键词：

D O I：

10.1016/0306-4549(79)90075-6

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：

It is found that the even-parity form of the neutron transport equation is well suited to a variational formulation in conjunction with the finite element approximation. A finite element technique is studied in the context of reactor physics calculations which is of particular interest in the nuclear engineering field. Multi-region slab problems for a given source distribution and critical slab problems are solved with an accuracy as good as the best problem techniques available. An exact solution is obtained for the special case of forward scattering with uniform source distribution in a slab reactor. © 1979.

引用

页码：205 / 223

页数：19

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