Use of Th and U in CANDU-6 and ACR-700 on the once-through cycle: Burnup analyses, natural U requirement/saving and nuclear resource utilization

被引:6
作者
Turkmen, Mehmet [1 ]
Zabunoglu, Okan H. [1 ]
机构
[1] Hacettepe Univ, Dept Nucl Engn, TR-06800 Ankara, Turkey
关键词
Thorium - Nuclear fuel reprocessing;
D O I
10.1016/j.jnucmat.2012.06.008
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Use of U and U-Th fuels in CANDU type of reactors (CANDU-6 and ACR-700) on the once-through nuclear fuel cycle is investigated. Based on the unit-cell approximation with the homogeneous-bundle/core model, utilizing the MONTEBURNS code, burnup computations are performed; discharge burnups are determined and expressed as functions of U-235 and Th fractions, when applicable. Natural Uranium Requirement (and Saving) and Nuclear Resource Utilization are calculated for varying fuel compositions. Results are analyzed to observe the effects of U-235 and Th fractions, thus to reach conclusions about use of Th in CANDU-6 and ACR-700 on the once-through cycle. (C) 2012 Elsevier B.V. All rights reserved.
引用
收藏
页码:263 / 269
页数:7
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