This unique publication provides an international overview onthe production and use of Zr alloys, their properties and behaviorduring nuclear service, the design of Zr components and theirtesting after service. Papers cover the historical aspects ofresearch on Zr alloys; basic metallurgy, including studies ofsecond phase particles; irradiation creep and growth; materialperformance during LOCA (loss of coolant accidents); and RIA(reactivity initiated accident).

Half of the papers in STP 1423 relate to corrosion and hydridingbehavior, the most important current issues in the industry. Aquarter of the papers deal with in-reactor studies. The remainingpapers discussed the behavior and properties of Zr alloys for theintermediate storage of spent fuel.

STP 1423 is a valuable resource for engineers and scientistsinvolved in the processing and properties of Zr alloys, theproduction and use of Zr alloy reactor components, their behaviorduring service and property changes that occur with increasingneutron fluences.

42 peer-reviewed papers provide an international overview of theproduction and use of Zr alloys.

Learn about:

• 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 theoxides formed during service