ASTM STP 1295-96

STP 1295 contains the most up-to-date information from the world’s leading experts on the use of zirconium-based alloys in water-cooled nuclear reactors. 41 peer-reviewed papers cover the following comprehensive topics: Corrosion Mechanisms Corrosion and Hydrogen Effects Ex-Reactor Mechanical Behavior In-Reactor Mechanical Behavior Effect of Irradiation on Microstructure Effects of Processing on Structures and Properties In-Reactor Behavior.