Microstructural Characterization of Irradiated U-7 Wt per cent Mo Dispersion Guels Wioth Al Alloy Matrices that Contain Si.

Keiser, D. D. ; Robinson, A. B. ; Jue, J. F. ; Wachs, D. M.

Technical Information Center Oak Ridge Tennessee

关键词: Nuclear fuel cycle;    Nuclear fuel materials;    Alloys;    Fabrication;    Fuel elements;   

RP-ID  :  DE2008938453

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

U-7Mo alloy dispersion fuels with Al alloy matrices that contain Si were irradiated in the Idaho National Laboratory (INL)s Advanced Test Reactor (ATR) and then destructively examined using optical metallography and scanning electron microscopy to characterize the developed microstructures. Results were compared to the microstructures of as-fabricated dispersion fuel to determine what changes had occurred during irradiation. It was found that having Si in the matrix resulted in the formation of Si rich fuel/matrix interaction layers around the fuel particles during the fuel element fabrication process. During irradiation, these interaction layers changed very little in thickness and in composition in many areas of a fuel plate that contained the most Si. However, in some rarely observed areas that were exposed to very aggressive irradiation conditions, the interaction layers grew in thickness and changed in composition to become Si-deficient. For a fuel plate with relatively low amounts of Si, only Si-deficient layers were observed. The overall irradiation performance to very high burnups was excellent for the fuel with the most Si in the Al alloy matrix.