Tensile Behavior of Cryorolled Zircaloy-2

Abstract

Zircaloy-2 is mainly used in nuclear technology, as cladding of fuel rods in nuclear reactors, especially water reactors (BWRs). Hence high strength of Zirca loy-2 is of prime importance. This investigation deals with the effect of cryorolling on Zircaloy-2 by co mparing d ifferent tensile properties. For this analysis, four samp les with various degrees of cryorolling are taken and tensile tests are conducted on these samples. The obtained results are analyzed and the optimu m degree of cryorolling of Zircaloy-2 is obtained. The cryorolling imp roved the mechanical properties of the material as the dislocations are entangled near the grain boundaries and also due to decrease in the grain size. The microstructure of the sample is analysed by optical microscope, before and after cryorolling and the grain structure analysis is done.