1. Modification of TRANSURANUS Fuel Performance Code in the ATF Framework;Abe,2019
2. Irradiation growth of zirconium alloys: a review;Adamson;Int. J. Nucl. Energy Sci. Technol.,2017
3. Assessment of Void Swelling in Austenitic Stainless Steel Core Internals (No. NUREG/CR-6897);Chung,2006
4. Falcon-based Comparative Assessment of Prototype Zr-4 and SiC Fuel Rod (No. 1022907),2011
5. Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys;Field;J. Nucl. Mater.,2015