44 papers discuss the history, processing, use, and properties of Zirconium and its alloys. Nearly half are concerned with the corrosion and hydriding of different Zirconium alloys. The techniques used to characterize the oxides and their microstructures and properties have become very advanced. The industry, including producers and users, expects that the work will lead to important conclusions about alloy development, optimization of the processing parameters, and station operating procedures so that the current and new Zirconium materials will continue to operate reliably to very high neutron fluences.
Seven major topics include:
Properties at High Neutron Fluences
Hydrogen and Temperature Effects
Deformation and Fracture Studies
Processing and Alloy Development
Effect of Composition and Microstructure on Corrosion
Corrosion Simulation and the Effect of the Environment
Effects of Oxides on Oxidation and H Pickup Rates
Audience:Scientists and engineers involved in the production and properties of components for use in nuclear reactors, their behavior during service and the property changes that occur with increasing neutron fluences.