Comparative study of actinide and fission product inventory of HEU and potential LEU fuels for MNSRs

被引：11
|
作者：
Waqar, Sadaf [1 ]
Mirza, Nasir M. [1 ]
Mirza, Sikander M. [1 ]
机构：
[1] PIEAS, Dept Appl Math & Phys, Islamabad 45650, Pakistan
来源：
PROGRESS IN NUCLEAR ENERGY | 2009年 / 51卷 / 01期
关键词：
Actinide and fission product inventory; HEU fuels; LEU fuels; MNSRs; REACTOR; ENRICHMENT;
D O I：
10.1016/j.pnucene.2008.02.002
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 comparative study of fuel burnup and buildup of actinides and fission products for potential LEU fuels (UO2 and U-9Mo) with existing HEU fuel (UAl4-Al, 90% enriched) for a typical Miniature Neutron Source Reactor (MNSR) has been carried-out using the WIMSD4 computer program. For the complete burnup to 0.042 g Pu-239 produced in case of UAl4-Al HEU core, UO2 and U-9Mo based cores have been found to yield 0.793 and 0.799 g, respectively, indicating much larger values of conversion rations and correspondingly high values of fuel utilization factor. The end-of-cycle activity of the HEU core has been found 2284 Ci which agrees well value found by Khattab where as for UO2 based and U-9Mo based LEU cores show 1.8 and 4.8% increase with values 2326 and 2394 Ci, respectively. (c) 2009 Elsevier Ltd. All rights reserved.
引用
收藏
页码：129 / 134
页数：6
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