Zirconium-Lost In Utopia

编/混：Lost In Utopia Zirconium alloys were developed for use as nuclear fuel cladding in the early 1950s Zirconium was chosen for use in the cores of water-cooled nuclear reactors because of its low thermal neutron capture cross-section, reasonable mechanical properties and adequate corrosion resistance in high temperature water. Although the use of Zr alloys has proven to be a good engineering solution, several properties are still subject to poor scientific understanding of their origins. Among them, deformation mechanisms (critical shear stresses on the different shear and twin systems), irradiation behavior (point defects interactions with alloying elements and mobilities), and corrosion mechanisms at atomic scales clearly need further basic scientific work. Reference: Cox B. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys[J]. Journal of Nuclear Materials, 2005, 336(2–3):331-368. Lemaignan C. 2.07 – Zirconium Alloys: Properties and Characteristics[J]. Comprehensive Nuclear Materials, 2012:217-232. 未经许可,不得翻唱或使用