This unique publication provides an international overview on the production and use of Zr alloys, their properties and behavior during nuclear service, the design of Zr components and their testing after service. Papers cover the historical aspects of research on Zr alloys; basic metallurgy, including studies of second phase particles; irradiation creep and growth; material performance during LOCA (loss of coolant accidents); and RIA (reactivity initiated accident).
Half of the papers in STP 1423 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 discussed the behavior and properties of Zr alloys for the intermediate storage of spent fuel.
STP 1423 is a valuable resource for engineers and scientists involved in the processing and properties of Zr alloys, the production and use of Zr alloy reactor components, their behavior during service and property changes that occur with increasing neutron fluences.
42 peer-reviewed papers provide an international overview of the production and use of Zr alloys.
Production and use of Zr alloys in the nuclear industry
Properties and behavior during nuclear service
Corrosion and hydriding during service
Dimensional changes during service
Design of Zr components
Testing after service
Effect of alloy microstructure and composition on behavior
Studies of the composition, properties and behavior of the oxides formed during service