Investigation of resistance of nuclear fuel cladding to hydride cracking

摘要

Zirconium alloys are used as structural materialsfor nuclear reactors. This is due to a combination of theproperties such as strength and ductility at reactor-operating temperatures, good corrosion resistance at hightemperatures and compatibility with fuel materials. Zirco-nium alloys are widely used for manufacturing of fuelcladdings, fuel spacer grids, pressure tubes and controlrods. However, zirconium, similar like titanium alloys aresusceptible to hydrogen [1, 2]. Zirconium phase has a verylow solubility of hydrogen, resulting in any excess hydro-gen getting precipitated as zirconium hydride. This leads toembrittlement [3], delayed hydride cracking (DHC) andhydride blistering, all of which limit the lifetime of reac-tors and cause serious safety and environmental concerns.