Analysis of NEA C5MOX benchmark with computer code "COHINT" based on interface current approach

被引：0
|
作者：
Mohanakrishnan, P [1 ]
机构：
[1] Indira Gandhi Ctr Atom Res, Reactor Phys Div, Kalpakkam 603102, Tamil Nadu, India
来源：
PROGRESS IN NUCLEAR ENERGY | 2004年 / 45卷 / 2-4期
关键词：
interface current approach; P-N half space expansion; C5MOX benchmark; computer code COHINT; square fuel rod;
D O I：
10.1016/j.pnucene.2004.09.005
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：
Interface current approach to solution of neutron transport equation has been earlier used for LWR lattice problems. The analysis of the C5MOX benchmark is a opportunity to test its applicability to heterogeneous reactor problem. Computer code COHINT, which incorporates a routine for solution of neutron transport equation in X-Y geometry by interface current approach was used for this analysis by representing the fuel rod as a square one. Region interface angular fluxes are represented by a four-term expansion. It is found that the average pin power error is about 2.28% (peak pin error 4.1%) relative to reference calculations. Further improvement is possible by introduction of the capability to represent circular rods with in a square cell in COHINT. (C) 2004 Published by Elsevier Ltd.
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收藏
页码：125 / 131
页数：7
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