1. Steam oxidation of Cr-coated zirconium alloy claddings at 1200 °C: kinetics transition and failure mechanism of Cr coatings;Deng;J. Nucl. Mater.,2023
2. Structural materials for fission & fusion energy;Zinkle;Mater. Today,2009
3. Neutron reflector materials (Be, hydrides);Kurosaki;Comprehensive Nuclear Materials,2020
4. Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation;Byun;J. Nucl. Mater.,2021
5. Development of advanced alloys with improved resistance to corrosion and stress corrosion cracking (SCC) in power plants;Prakash,2014