Full Description

STP 1295 contains the most up-to-date information from the world's leading experts on the use ofzirconium-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.

Product Details

Published: 01/01/1996 Number of Pages: 925