Zirconium in Nuclear Applications

Front Cover
ASTM International, 1974 - Nuclear reactors
 

Contents

Introduction
3
Zirconium for Nuclear Primary Steam Systems
5
Development of a ClosedEnd Burst Test Procedure for Zircaloy Tubing
14
Uniform Ultrasonic Inspection of Fuel Sheath Tubing
31
Defect Sensitivity in Lamb Wave Testing of ThinWalled Tubing
39
Improved Metallography of Zirconium Alloys
52
Determination of Solid Solubility Limit of Hydrogen in Alpha Zirconium by Internal Friction Measurements
63
Dual Analysis of Longitudinal and Transverse Zirconium Tensile StressStrain Data
75
Mechanisms of Irradiation Creep in ZirconiumBase Alloys
229
InReactor Creep of Zr25Nb Tubes at 570 K
249
InReactor Stress Relaxation of Zirconium Alloys
263
High Deformation Creep Behavior of 06in Diameter Zirconium Alloy Tubes Under Irradiation
274
Suppression of Void Formation in Zirconium
292
Deformation of Irradiated ZirconiumNiobium AI Ioys
309
Variation of Zircaloy Fracture Toughness in Irradiation
328
Strength and Ductility of Neutron Irradiated and Textured Zircaloy2
355

Determination of Complete PlaneStress Yield Loci of Zircaloy Tubing
92
Effect of Thermomechanical Processing and Heat Treatment on the Properties of Zr3NblSn Strip and Tubing
104
Potential for Improvement of Mechanical Properties in Zircaloy ColdRolled Strip and Sheet
129
Effect of the Annealing Temperature on the Creep Strength of ColdWorked Zircaloy4 Cladding
140
Thermomechanical Control of Texture and Tensile Properties of Zircaioy4 Plate
146
Creep Strength of Zircaloy Tubing at 400C as Dependent on Metallurgical Structure and Texture
160
Pilger Tooling Design for Texture Control
169
Discussion
177
Operable Deformation Systems and Mechanical Behavior of Textured Zircaloy Tubing
179
Discussion
199
Directionality of the Grain Boundary Hydride in Zircaloy2
201
Use of Ion Bombardment to Study Irradiation Damage in Zirconium Alloys
213
Plastic Instability in Irradiated ZrSn and ZrNb Alloys
370
Assessment of Fracture Studies on Zircaloy2 Pressure Tubes
385
Irradiation Damage Recovery in Some Zirconium Alloys
400
Stress Corrosion Cracking of Zircaloys in Iodine Containing Environments
417
Microstructure of the Oxide Films on ZirconiumBased Alloys Formed
435
Corrosion and Hydriding Performance of Zircaloy Tubing After Extended Exposure in the Shippingport Pressurized Water Reactor
449
Discussion
461
Characterization of Zircaloy Oxidation Films
463
Discussion
478
Fracture of Zircaloy2 in an Environment Containing Iodine
479
Study of Zirconium Alloy Corrosion Parameters in the Advanced Test Reactor
495
Effect of Surface Treatment on the Irradiation Enhancement of Corrosion of Zircaloy2 in HBWR
514

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