Thermal and mechanical properties of light-water reactor cladding materials

Abstract

This thesis is a literature review on the thermal and mechanical properties of cladding materials for light-water reactors. In this thesis, zirconium-based alloys and novel accident-tolerant materials in various properties will be compared to evaluate their safety and applicability in reactors. This thesis presents the historical development of cladding technology. Zirconium alloys have occupied an important position in history due to their low neutron absorption and strong corrosion resistance. However, their limitation of being prone to oxidation at high temperatures has also prompted people to turn to the development of ATF. This thesis selects chromium-coated zirconium, FeCrAl alloys and SiC/SiC composites as candidate materials for ATF. According to the comparison, SiC/SiC composites show the strongest high-temperature stability and accident tolerance, FeCrAl alloys are relatively balanced between strength and manufacturability, and chromium-coated zirconium is the most compatible with existing reactor types. In conclusion, chromium-coated zirconium and FeCrAl alloys are more suitable for current deployment, while SiC/SiC composites still needs further efforts to solve brittleness problems.