Small-Scale Specimen Testing of Monolithic U-Mo Fuel Foils. RERTR 2008.

Prabhakaran, R. ; Burkes, D. E. ; Wachs, D. M. ; Cole, J. I. ; Charit, I.

Technical Information Center Oak Ridge Tennessee

关键词: Nuclear reactor fuels;    Irradiated fuels;    Tensile behavior;    Fabrication;    Mechanical properties;   

RP-ID  :  DE2008941732

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The objective of this investigation is to develop a shear punch testing (SPT) procedure and standardize it to evaluate the mechanical properties of irradiated fuels in a hot-cell so that the tensile behavior can be predicted using small volumes of material and at greatly reduced irradiation costs. This is highly important in the development of low-enriched uranium fuels for nuclear research and test reactors. The load-displacement data obtained using SPT can be interpreted in terms of and correlated with uniaxial mechanical properties. In order to establish a correlation between SPT and tensile data, sub-size tensile and microhardness testing were performed on U-Mo alloys. In addition, efforts are ongoing to understand the effect of test parameters (such as specimen thickness, surface finish, punch-die clearance, crosshead velocity and carbon content) on the measured mechanical properties, in order to rationalize the technique, prior to employing it on a material of unknown strength.