Calculation of the pin power distribution for a thorium reactor assembly and benchmarking

被引：0
|
作者：
Aziz, M. [1 ]
机构：
[1] Atom Energy Author, Natl Ctr Nucl Safety, Cairo, Egypt
来源：
KERNTECHNIK | 2007年 / 72卷 / 1-2期
关键词：
Nuclear reactors;
D O I：
10.3139/124.100315
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 computer model was developed to perform neutronic and burn-up analysis for an assembly of a thorium reactor The MCNP computer code was used to model the geometry of the assembly and to determine both, the power and flux distribution. A system of ordinary differential equations which represents all fuel isotopes was solved numerically to evaluate the time behavior of fuel composition and burn-up. The results of the present model were compared with the solutions of benchmark problems and satisfactory agreement was found.
引用
收藏
页码：33 / 37
页数：5
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