Mechanical Properties of DU-xMo Alloys with x=7 to 12 Weight Percent

被引:43
作者
Burkes, Douglas E. [1 ]
Prabhakaran, Ramprashad [2 ]
Jue, Jan-Fong [1 ]
Rice, Francine J. [1 ]
机构
[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA
[2] Univ Idaho, Mat Sci & Engn Dept, Moscow, ID 83844 USA
来源
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE | 2009年 / 40A卷 / 05期
基金
美国能源部;
关键词
IRRADIATION BEHAVIOR; URANIUM; MOLYBDENUM; TENSILE; FUELS;
D O I
10.1007/s11661-009-9805-5
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Mechanical properties of six depleted uranium-molybdenum (U-Mo) alloys have been obtained using microhardness, quasistatic tensile tests, and scanning electron microscopy (SEM) failure analysis. U-Mo alloy foils are currently under investigation for potential conversion of high power research reactors to low enriched uranium fuel. Although mechanical properties take on a secondary effect during irradiation, an understanding of the alloy behavior during fabrication and the effects of irradiation on the integrity of the fuel is essential. In general, the microhardness, yield strength, Young's modulus, and ultimate tensile strength improved with increasing Mo content. Microhardness measurements were very sensitive to local composition, while the failure mode was significantly controlled by the impurity concentration of the alloy, especially carbon. Values obtained from literature are also provided with reasonable agreement, even though processing conditions and applications were quite different in some instances.
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页码:1069 / 1079
页数:11
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