共 50 条
- [31] CORROSION RESISTANCE OF TRADITIONAL AND ADVANCED FUEL ROD CLADDING MATERIALS FOR WATER-COOLED REACTORS USPEKHI FIZIKI METALLOV-PROGRESS IN PHYSICS OF METALS, 2024, 25 (02): : 243 - 275
- [38] Effect of Local Hydride Accumulations on Zircaloy Cladding Mechanical Properties ZIRCONIUM IN THE NUCLEAR INDUSTRY: 15TH INTERNATIONAL SYMPOSIUM, 2009, 1505 : 141 - +
- [40] RESEARCH AND DEVELOPMENT OF NOVEL MATERIALS FOR ACCIDENT TOLERANT FUEL CLADDING OF NUCLEAR REACTORS EAST EUROPEAN JOURNAL OF PHYSICS, 2020, (04): : 75 - 83