Cermet fuel for fast reactor - Fabrication and characterization

被引：7
|
作者：
Mishra, Sudhir [1 ]
Kutty, P. S. [1 ]
Kutty, T. R. G. [1 ]
Das, Shantanu [2 ]
Dey, G. K. [3 ]
Kumar, Arun [1 ]
机构：
[1] Bhabha Atom Res Ctr, Radiomet Div, Bombay 400085, Maharashtra, India
[2] Bhabha Atom Res Ctr, Uranium Extract Div, Bombay 400085, Maharashtra, India
[3] Bhabha Atom Res Ctr, Div Mat Sci, Bombay 400085, Maharashtra, India
来源：
JOURNAL OF NUCLEAR MATERIALS | 2013年 / 442卷 / 1-3期
关键词：
US PERSPECTIVE; INERT MATRIX; EBR-II; EXPERIENCE; ALLOYS;
D O I：
10.1016/j.jnucmat.2013.08.051
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
(U, Pu)O-2 ceramic fuel is the well-established fuel for the fast reactors and (U, Pu, Zr) metallic fuel is the future fuel. Both the fuels have their own merits and demerits. Optimal solution may lie in opting for a fuel which combines the favorable features of both fuel systems. The choice may be the use of cermet fuel which can be either (U, PuO2) or (Enriched U, UO2). In the present study, attempt has been made to fabricate (Natural U, UO2) cermet fuel by powder metallurgy route. Characterization of the fuel has been carried out using dilatometer, differential thermal analyzer, X-ray diffractometer, and Scanning Electron Microscope. The results show a high solidus temperature, high thermal expansion, presence of porosities, etc. in the fuel. The thermal conductivity of the fuel has also been measured. X-ray diffraction study on the fuel compact reveals presence of alpha U and UO2 phases in the matrix of the fuel. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码：400 / 407
页数：8
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