Determination of the LEU core safety parameters of the MNSR reactor using the MCNP4C code

被引：2
|
作者：
Dawahra, S. [1 ]
Khattab, K. [1 ]
Saba, G. [1 ]
机构：
[1] Atom Energy Commiss, Dept Nucl Engn, Damascus, Syria
来源：
ANNALS OF NUCLEAR ENERGY | 2014年 / 63卷
关键词：
The excess reactivity (rho(ex)); The control rod worth (CRW); The shutdown margin (SDM); The safety reactivity factor (SRF); The delayed neutron fraction (beta(eff));
D O I：
10.1016/j.anucene.2013.08.033
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：
Comparative studies for the conversion of the fuel from HEU to LEU in the Miniature Neutron Source Reactor (MNSR) have been performed using the MCNP4C code. The safety parameters like: the effective multiplication factor (k(eff)), excess reactivity (rho(ex)), control rod worth (CRW), shutdown margin (SDM), safety reactivity factor (SRF) and delayed neutron fraction (beta(eff)) for the existing HEU fuel (UAl4-Al, 90% enriched) and the potential LEU fuels (U3Si2-Al, U3Si-Al and the U9Mo-Al, 19.75% enriched) were investigated in this paper for the MNSR using the MCNP4C code. The results showed for the existing HEU fuel and the potential LEU fuels that the control rod shutdown margins were: 2.587, 2.295, 2.325 and 2.165 mk. The control rod worths were: 6.54, 6.16, 6.09 and 6.05 mk. The safety reactivity factors were: 1.648, 1.588, 1.611 and 1.551. The delayed neutron fractions were calculated to be: 7.54 x 7.48 x 10(-3), 7.29 x 10(-3) and 7.57 x 10(-3) for the UAl4-Al, U3Si2-Al, U3Si-Al and the U9Mo-Al fuels respectively. Finally, the safety parameters of the LEU fuels are in good agreements with HEU results and all types of the LEU fuels can be suitable candidates for the fuel conversion in the future. (C) 2013 Elsevier Ltd. All rights reserved.
引用
收藏
页码：594 / 597
页数：4
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