In-situ study on the tensile property and fracture behavior of Cr coating for nuclear fuel cladding

Abstract It has been suggested that Cr-coated zircaloy is an excellent material for accident-tolerant fuel (ATF) cladding. found Cr coating shows multi-cracking behavior under external load due to its embrittlement. Different fabrication parameters will lead different crack resistances of the coatings, but brittle cracking characteristic common. The estimation strength and structural integrity cladding depend on coating. coating’s tensile ATF was examined utilizing in-situ mechanical testing method. surface initiation, propagation, fracture process were captured in real time, density evolution two compared. results demonstrate first long channel occurs at a small strain, then increases rapidly gradually reaches saturation with increasing stress. change resistance. Compared previous sample, new sample started larger reached faster saturated density, resistance inferior. Many cracks directions observed near surface. Moreover, there no interfacial spallation stress, demonstrating adhesive property.