Optimisation of inert matrix fuel concepts for americium transmutation

被引：84
|
作者：
Chauvin, N [1 ]
Konings, RJM
Matzke, H
机构：
[1] Comm Energie Atom, Ctr Cadarache, F-13108 St Paul Les Durance, France
[2] NRG, NL-1755 ZG Petten, Netherlands
[3] Commiss European Communities, Inst Transuranium Elements, D-7500 Karlsruhe, Germany
来源：
JOURNAL OF NUCLEAR MATERIALS | 1999年 / 274卷 / 1-2期
关键词：
D O I：
10.1016/S0022-3115(99)00078-1
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Concepts of inert-matrix fuels for americium transmutation are discussed. It is demonstrated that a 'hybrid' fuel design, consisting in a dispersion of an americium-bearing phase in an inert matrix, is desirable. More than a solid-solution is preferred in order to localise within a small volume the damage in the matrix due to fission fragments. Such a dispersion is composed of spherical inclusions (between 50 and 300 mu m) of an americium host phase in a dense inert matrix. For an oxide fuel, we recommend the solid solution (Zr,Am)O-2, possibly stabilised by yttrium as the host phase. For a nitride fuel, (Zr,Am)N is proposed. MgO and MgAl2O4 (oxide fuel), as well as TiN and ZrN (nitride fuel) are the most likely candidates for the inert matrix. Recommendations are also given for the research required to optimise the concept. (C) 1999 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：105 / 111
页数：7
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