Characterization of Interaction Layer in U-Mo-X (X = Nb, Zr) and U-Nb-Zr vs. Al Diffusion Couples Annealed at 600°C for 10 Hours

被引:3
|
作者
Ewh, A. [1 ]
Perez, E. [1 ]
Keiser, D. D., Jr. [2 ]
Sohn, Y. H. [1 ]
机构
[1] Univ Cent Florida, Dept Mech Mat & Aerosp Engn, Adv Mat Proc & Anal Ctr, 4000 Cent Florida Blvd, Orlando, FL 32816 USA
[2] Nucl Fuels & Mat Div, Idaho Natl Lab, Idaho Falls, ID 83415 USA
关键词
Fuel-cladding interaction; metallic nuclear fuels; uranium alloys; diffusion;
D O I
10.4028/www.scientific.net/DDF.312-315.1055
中图分类号
O64 [物理化学(理论化学)、化学物理学];
学科分类号
070304 ; 081704 ;
摘要
U-Mo has thus far proven to be one of the most feasible metallic fuel alloys for use in research and test reactors due to its high density and stability during irradiation. However, an adverse diffusional interaction can occur between the fuel alloy and the Al based matrix. This forms an interaction layer (IL) that has undesirable thermal properties and irradiation behavior leading to accelerated swelling and reduced fuel efficiency. This study focused on the effects of ternary alloying additions on the formation of IL between U based alloys and Al. Diffusion couples of U-8Mo-3Nb, U-7Mo-6Zr, and U-10Nb-4Zr (wt.%) vs. pure Al were assembled and annealed at 600 degrees C for 10 hours. Both thickness and phase constituent analyses were performed via electron microscopy. The major phase constituent of the IL was determined to be the UAl3 intermetallic compound. The Nb and Zr alloying additions did not reduce growth rate of IL (1.3 similar to 1.4 mu m/sec(1/2)) as compared to couples made between binary U-Mo and Al (0.9 similar to 1.8 mu m/sec(1/2)).
引用
收藏
页码:1055 / +
页数:3
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