Purex co-processing of spent LWR fuels:: flow sheet

被引:18
|
作者
Zabunoglu, OH [1 ]
Özdemir, L [1 ]
机构
[1] Hacettepe Univ, Dept Nucl Engn, Ankara, Turkey
关键词
D O I
10.1016/j.anucene.2004.07.015
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
Purex co-processing of spent LWR fuel is investigated. In purex co-processing, uranium and plutonium in spent fuel are processed and recovered together as a single stream, while in standard purex reprocessing uranium and plutonium are obtained as separate streams. A two-step (co-decontamination and co-stripping) flow sheet for purex co-processing is devised; concentrations, recoveries and decontamination factors are calculated; and methods to co-convert uranium-plutonium nitrate to mixed oxide are reviewed. A closed nuclear fuel cycle in which at no point uranium and plutonium are separated from each other is reached. (C) 2004 Elsevier Ltd. All rights reserved.
引用
收藏
页码:151 / 162
页数:12
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