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

页码：626 / 631

页数：6

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