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Digital Library/Symposia/B10/Zirconium in the Nuclear Industry
Sponsored by ASTM committee B10 on Reactive and Refractory Metals and Alloys
June 24 2007 - June 28 2007

 Papers Published from this Symposium
Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5 Alloys in LOCA Conditions
Corrosion and Oxide Properties of HANA Alloys
Experimental and Analytical Investigation of the Mechanical Behavior of High-Burnup Zircaloy-4 Fuel Cladding
A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor
Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys
Investigations of the Microstructure and Mechanical Properties of Prior- Structure as a Function of the Oxygen Content in Two Zirconium Alloys
 
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