Article ID Journal Published Year Pages File Type
5454375 Journal of Nuclear Materials 2016 7 Pages PDF
Abstract
A dilute Zr alloy containing 0.3% Sn (a potential material for liner applications of composite fuel claddings of thermal nuclear power reactors) was subjected to controlled uniaxial compression over a wide range of strain rates and temperatures in a thermo-mechanical simulator. The evolved microstructures were characterized using SEM based EBSD technique and the texture evolution was analysed by bulk X-ray diffraction method. The study had brought out the systematic changes brought out in microstructure and texture as a function of temperature and strain rate. The results indicate that a temperature of 750 °C is the optimum temperature for hot deformation of this alloy in terms of achieving a homogenous and well recrystallized microstructure.
Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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