NUMERICAL SOLUTION OF NEUTRON TRANSPORT EQUATION

被引：3

作者：

BOWDEN, RL

BULLARD, AG

机构：

[1] Department of Physics, Virginia Polytechnic Institute, Blacksburg, VA

来源：

JOURNAL OF NUCLEAR ENERGY | 1969年 / 23卷 / 11-1期

关键词：

D O I：

10.1016/0022-3107(69)90021-5

中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

学科分类号：

0807 ; 0820 ;

摘要：

An outline of a procedure for directly solving the singular integral form of the one-speed neutron transport equation is given. The procedure is illustrated by considering the Milne problem and a one-region critical problem. Examples of numerical results obtained for these two problems are presented. © 1969.

引用

页码：655 / &

共 9 条

[1]

BAREISS EH, 1965, ANL6988 REP

[2]

BOWDEN RL, 1968, T AM NUCL SOC, V11, P317

[3] SOLUTION OF TRANSPORT EQUATION WITH ANISOTROPIC SCATTERING IN SLAB GEOMETRY [J].