Investigations of Aluminum-Doped Self-Healing Zircaloy Surfaces in Context of Accident-Tolerant Fuel Cladding Research

A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment

(2015) Dong Jun Park et al.   CORROSION SCIENCE

Interdiffusion and reaction between Zr and Al alloys from 425° to 625 °C

(2014) J. Dickson et al.   INTERMETALLICS

Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure

(2013) Kurt A. Terrani et al.   JOURNAL OF NUCLEAR MATERIALS

A review on the clad failure studies

(2011) Tanweer Alam et al.   NUCLEAR ENGINEERING AND DESIGN

Corrosion monitoring and determination of aluminium fuel clad of Tehran Research Reactor (TRR)

(2009) R. Gholizadeh Aghoyeh et al.   PROGRESS IN NUCLEAR ENERGY

Oxidation of aluminum alloy cladding for research and test reactor fuel

(2008) Yeon Soo Kim et al.   JOURNAL OF NUCLEAR MATERIALS