Beta-Quenched Zircaloy-4
A Model for Channel Behaviour During Cyclic Deformation of Neutron Irradiated Copper
The Influence of Radiation-induced Lattice Defects on the Fatigue Properties of Copper Single Crystals
Zirconium in the Nuclear Industry
The Effect of Mercury on the Fatigue Behavior of Copper
Methods for the Evaluation and Design of Light-pipe Systems for Commercial Buildings
Development of New Zirconium Alloys for a BWR
Zircaloy-2 Lined Zirconium Barrier Fuel Cladding
Corrosion Behavior of Irradiated Zircaloy
Zirconium-Barrier Cladding Attributes
High-Temperature Irradiation Growth in Zircaloy
High-Fluence Irradiation Growth of Zirconium Alloys at 644 to 725 K
Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2
Performance of Irradiated Copper and Zirconium Barrier-Modified Zircaloy Cladding Under Simulated Pellet-Cladding Interaction Conditions
Fatigue Behavior of Irradiated and Unirradiated Zircaloy and Zirconium
Zirconium in the Nuclear Industry
Failure Strain for Irradiated Zircaloy Based on Subsized Specimen Testing and Analysis
Texture Measurement Techniques for Zircaloy Cladding
Development of a Sensitive and Reproducible Steam Test for Zircaloy Nodular Corrosion