Fabrication and microstructure characterization of inert matrix fuel based on yttria stabilized zirconia

被引：20

作者：

Hellwig, C ^{[1
]}

Pouchon, M ^{[1
]}

Restani, R ^{[1
]}

Ingold, F ^{[1
]}

Bart, G ^{[1
]}

机构：

[1] Paul Scherrer Inst, Nucl Energy & Safety Dept, CH-5232 Villigen, Switzerland

来源：

JOURNAL OF NUCLEAR MATERIALS | 2005年 / 340卷 / 2-3期

关键词：

D O I：

10.1016/j.jnucmat.2004.11.004

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The deployment of a suitable, Pu-bearing inert matrix fuel (IMF) could offer an attractive option as a single-recycling LWR strategy aimed at reducing the currently growing plutonium stockpiles. A development programme focusing on yttria stabilized zirconia (YSZ)-based IMF is conducted at PSI. YSZ-based IMF has so far been irradiated in two test reactors. The fabrication routes as well as the characterization of the irradiated material by ceramography, electronprobe microanalysis, and X-ray diffraction are presented. IMF fabrication by attrition milling of the oxide constituents is possible, but high sintering temperatures are required to achieve homogeneity. X-ray diffraction is a suitable tool to monitor the homogeneity. Extra efforts are needed to increase the density. (c) 2004 Elsevier B.V. All rights reserved.

引用

页码：163 / 170

页数：8

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