10 MW research reactor simulation using fuel plate type

被引:2
|
作者
Mustafa, M. El Sayed [1 ]
Shaat, M. [1 ]
El Kady, M. [2 ]
机构
[1] Nucl Res Ctr, Reactors Dept, Inshas, Egypt
[2] Al Azhar Univ, Dept Power Mech Engn, Fac Engn, Cairo, Egypt
关键词
Thermal hydraulics;
D O I
10.1016/j.nucengdes.2016.01.006
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 code was established named ET-RR-1-10 to investigate the thermal hydraulic behavior of the ETRR1 (first Egyptian research reactor) research reactor when its power upgraded to 10 MW using the new fuel plate elements type. The work done include both normal and flow reduction conditions. The code modeled primary loop, secondary lop, and reactor kinetics. All code models used finite difference technique. The code results were tested against the available corresponding experimental data taken from a similar research reactor MITR (Massachusetts Institute of Technology research reactor) for the sake of code validation. The results showed good agreement, and the code can be used for thermal hydraulic calculations. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码:34 / 40
页数:7
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