REVIEW OF 15 YEARS OF HIGH-DENSITY LOW-ENRICHED UMo DISPERSION FUEL DEVELOPMENT FOR RESEARCH REACTORS IN EUROPE

被引:91
|
作者
Van den Berghe, S. [1 ]
Lemoine, P. [2 ]
机构
[1] Nucl Mat Sci Inst NMS, SCK CEN, B-2400 Mol, Belgium
[2] CEA, CEA Saclay, Direct Energie Nucl, F-91191 Gif Sur Yvette, France
关键词
Uranium-molybdenum U-Mo; Nuclear Fuel; LEU; Research Reactor; WT-PERCENT-MO; IRRADIATION BEHAVIOR; POSTIRRADIATION EXAMINATION; INDUCED RECRYSTALLIZATION; NONDESTRUCTIVE ANALYSES; ALLOY; URANIUM; ALUMINUM; U3SI2; SI;
D O I
10.5516/NET.07.2014.703
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
This review aims to provide a synthesis of the knowledge generated and the lessons learned in roughly 15 years of UMo dispersion fuel R&D in Europe through a series of irradiation experiments. A lot of irradiations were also performed outside of Europe, particularly in the USA, Russia, Canada, Korea and Argentina. In addition, a large number of out-of-pile investigations were done throughout the world, providing support to the understanding of the phenomena governing the UMo behaviour in pile. However, the focus of this article will be on the irradiations and Post-Irradiation Examination (PIE) results obtained in European experiments. The introduction of the article provides a historic overview of the evolution and progress in the high density UMo dispersion fuel development. The ensuing sections then provide further details on the various phases of the development, from the UMo dispersion in a pure A1 matrix through the addition of Si to the matrix to address the interaction layer formation and finally to the more advanced solutions to the excessive swelling encountered in various experiments. This review was based only on published results or results that are currently in the process of being published.
引用
收藏
页码:125 / 146
页数:22
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