Forty-two peer-reviewed papers provide an international overview on the production and use of zirconium alloys, their properties and behavior during nuclear service, the design of zirconium components and their testing after service. Forty-two peer-reviewed papers cover the historial aspects of research on zirconium alloys; basic metallurgy, including studies of second hase particles; irradiation creep and growth; material performance during LOCA (loss of collant accidents); and RIA (reactivity initiated accident).
Half of the papers in this unique publication relate to corrosion and hydriding behavior, the most important current issues in the industry. A quarter of the papers deal with in-reactor studies. The remaining papers discuss the behavior and properties of zirconium alloys for the intermediate storage of spent fuel.
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