Zirconium in Nuclear Applications

Front Cover
ASTM International, 1974
 

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Contents

Introduction
3
Development of a ClosedEnd Burst Test Procedure for Zircaloy Tubing
14
Uniform Ultrasonic Inspection of Fuel Sheath Tubing B T CROSS
31
Defect Sensitivity in Lamb Wave Testing of ThinWalled Tubing
39
Improved Metallography of Zirconium Alloys P D kaufmann
52
Determination of Solid Solubility Limit of Hydrogen in Alpha
63
Plastic Deformation
70
Determination of Complete PlaneStress Yield Loci of Zircaloy
92
InReactor Creep of Zr2 5Nb Tubes at 570 K E F IBRAHIM
249
InReactor Stress Relaxation of Zirconium Alloys A R CAUSEY
263
High Deformation Creep Behavior of 0 6in Diameter Zirco
274
Suppression of Void Formation in Zirconium M H YOO
292
Deformation of Irradiated ZirconiumNiobium Alloys C E ELLS 311
312
Variation of Zircaloy Fracture Toughness in Irradiation
328
Strength and Ductility of Neutron Irradiated and Textured
355
Plastic Instability in Irradiated ZrSn and ZrNb Alloys
370

Effect of Thermomechanical Processing and Heat Treatment
104
Potential for Improvement of Mechanical Properties in Zircaloy
129
Effect of the Annealing Temperature on the Creep Strength
140
Thermomechanical Control of Texture and Tensile Properties
146
Creep Strength of Zircaloy Tubing at 400 C as Dependent
160
Pilger Tooling Design for Texture Control J H SCHEMEL
169
Operable Deformation Systems and Mechanical Behavior
179
Directionality of the Grain Boundary Hydride in Zircaloy2
201
Use of Ion Bombardment to Study Irradiation Damage in Zir
213
Mechanisms of Irradiation Creep in ZirconiumBase Alloys
229
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
417
Microstructure of the Oxide Films Formed on ZirconiumBased
435
Corrosion and Hydriding Performance of Zircaloy Tubing After
449
Characterization of Zircaloy Oxidation Films A w URQUHART
463
Fracture of Zircaloy2 in an Environment Containing Iodine
479
Study of Zirconium Alloy Corrosion Parameters in the Advanced
495
Effect of Surface Treatment on the Irradiation Enhancement
514
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