Inert matrix fuel for the utilisation of plutonium

被引:62
作者
Ledergerber, G [1 ]
Degueldre, C
Heimgartner, P
Pouchon, MA
Kasemeyer, U
机构
[1] Kernkraftwerk Leibstadt AG, CH-5325 Leibstadt, Switzerland
[2] Paul Scherrer Inst, CH-5232 Villigen, Switzerland
关键词
inert matrix fuel; plutonium; nuclear fuel; nuclear energy; yttria stabilised zirconia;
D O I
10.1016/S0149-1970(00)00122-0
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Utilising fuel resources responsibly, reducing waste volume and emissions as well as conflict potentials within the international community (non-proliferation, energy demand) are among the principles for the judgement of sustainable development. Utilising and burning plutonium in a light water reactor has been shown to be feasible for the disposition of the large amount of excess plutonium produced in today's power reactors and resulting from the disarmament efforts of the super powers. With regard to material technology aspects, efforts have concentrated on the evaluation of fabrication feasibility and on the determination of the physicochemical properties of a single phase zirconium/erbium/plutonium oxide material stabilised as a cubic solution by yttrium for plutonium and minor actinide incineration and transmutation. Due to the absence of uranium as origin for plutonium build-up, such a nuclear fuel is called Inert Matrix Fuel. Irradiation testing with a dedicated experiment in the material test reactor in Halden, Norway, is underway within the framework of the OECD-Halden Reactor Project. (C) 2001 Elsevier Science Ltd. All rights reserved.
引用
收藏
页码:301 / 308
页数:8
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