Objective and Scope

The purpose of the symposium is to provide a forum for exchanging new information on the fabrication, testing, development, and characterization of both traditional and new zirconium-based materials used in the nuclear industry, including materials performance during normal, transient, and accident conditions as well as materials behavior during intermediate and long-term storage conditions. Of particular interest are studies that focus on identifying and understanding the mechanisms and behaviors of zirconium-based materials.

Appropriate topics for papers include, but are not limited to, the following:

• Basic Metallurgy and Processing
• Fabrication and Alloy Development
• Mechanical Behavior
• Corrosion and Hydriding
• In-Reactor Performance
• Irradiation Effects
• High-Temperature and Transient Phenomena
• Mechanistic Modeling of Processing or Performance
• Intermediate and Long-Term Storage Performance
• Coatings for Accident Tolerant Fuel

The language of the symposium will be English.

Both oral and poster presentations are planned. The John Schemel Award for the best paper of the symposium will be selected from the submitted papers. The best poster will also be recognized at the symposium.