Sintering densification of CaO-UO2-Gd2O3 nuclear fuel pellets

被引：4
|
作者：
Wang, Yun [1 ]
Sun, Huidong [2 ]
Wang, Hui [3 ]
Pan, Xiaoqiang [3 ]
Li, Tongye [3 ]
Liu, Jinhong [3 ]
Zhang, Yong [3 ]
Wang, Xinjie [3 ]
机构：
[1] E China Inst Technol, Fundamental Sci Radioact Geol & Explorat Technol, Nanchang 330013, Jiangxi, Peoples R China
[2] China Nucle Power Engn Co Ltd, Beijing, Peoples R China
[3] Nucl Power Inst China, Natl Key Lab Nucl Fuel & Mat, Chengdu 610041, Peoples R China
来源：
JOURNAL OF ALLOYS AND COMPOUNDS | 2015年 / 646卷
基金：
中国国家自然科学基金;
关键词：
Advanced nuclear fuel; Burnable poison; Sintering densification; Co-precipitation reaction method; High burn-up;
D O I：
10.1016/j.jallcom.2015.05.278
中图分类号：
O64 [物理化学（理论化学）、化学物理学];
学科分类号：
070304 ; 081704 ;
摘要：
CaO-doped UO2-10 wt% Gd2O3 burnable poison fuel was prepared by co-precipitation reaction method. It was found that 0.3 wt% CaO-doping significantly improved the sintered density, grain sizes and crushing strength of UO2-Gd2O3 fuel pellets at the sintering temperature of 1650 degrees C in the sintering atmosphere of hydrogen for 3.5 h. In addition, homogeneous solid solution without precipitation of free phases of CaO and Gd2O3 was successfully achieved. CaO doping in UO2-Gd2O3 fuel pellet system accelerated the thermally activated material transport, so the onset temperature of densification as well as the temperature of the maximum densification rate shifted to a lower temperature region. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码：626 / 631
页数：6
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