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Zirconium in Nuclear Applications Schemel JH Pages: 523       Published: 1974

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Table of Contents

Introduction
Schemel JH, Rosenbaum HS

Discussion


Discussion


Discussion


Discussion


Zirconium for Nuclear Primary Steam Systems
Webster RT

Development of a Closed-End Burst Test Procedure for Zircaloy Tubing
Hardy DG, Stewart JR, Lowe AL

Uniform Ultrasonic Inspection of Fuel Sheath Tubing
Cross BT, Abbott DJ

Defect Sensitivity in Lamb Wave Testing of Thin-Walled Tubing
Wiklund J

Improved Metallography of Zirconium Alloys
Kaufmann PD, Danielson P, Baroch EF

Determination of Solid Solubility Limit of Hydrogen in Alpha Zirconium by Internal Friction Measurements
Mishra S, Asundi MK

Dual Analysis of Longitudinal and Transverse Zirconium Tensile Stress-Strain Data
Garde AM, Reed-Hill RE

Determination of Complete Plane-Stress Yield Loci of Zircaloy Tubing
Dressler G, Drefahl K, Matucha K-H, Wincierz P

Effect of Thermomechanical Processing and Heat Treatment on the Properties of Zr-3Nb-1Sn Strip and Tubing
Curtis RE, Dressler G

Potential for Improvement of Mechanical Properties in Zircaloy Cold-Rolled Strip and Sheet
Kaufmann PD, Baroch EF

Effect of the Annealing Temperature on the Creep Strength of Cold-Worked Zircaloy -4 Cladding
Frenkel JM, Weisz M

Thermomechanical Control of Texture and Tensile Properties of Zircaloy-4 Plate
Dahl JM, McKenzie RW, Schemel JH

Creep Strength of Zircaloy Tubing at 400°C as Dependent on Metallurgical Structure and Texture
Källström K, Andersson T, Hofvenstam A

Pilger Tooling Design for Texture Control
Schemel JH, McKenzie RW

Operable Deformation Systems and Mechanical Behavior of Textured Zircaloy Tubing
Tenckhoff E

Directionality of the Grain Boundary Hydride in Zircaloy-2
Kawanishi H, Ishino S, Mishima Y

Use of Ion Bombardment to Study Irradiation Damage in Zirconium Alloys
Adamson RB, Bell WL, Lee D

Mechanisms of Irradiation Creep in Zirconium-Base Alloys
Dollins CC, Nichols FA

InReactor Creep of Zr2.5Nb Tubes at 570 K
Ibrahim EF

InReactor Stress Relaxation of Zirconium Alloys
Causey AR

High Deformation Creep Behavior of 0.6-in.-Diameter Zirconium Alloy Tubes Under Irradiation
Wood DS

Suppression of Void Formation in Zirconium
Yoo MH

Deformation of Irradiated Zirconium-Niobium Alloys
Ells CE

Variation of Zircaloy Fracture Toughness in Irradiation
Walker TJ, Kass JN

Strength and Ductility of Neutron Irradiated and Textured Zircaloy-2
Rieger GF, Lee D

Plastic Instability in Irradiated Zr-Sn and Zr-Nb Alloys
Cheadle BA, Ellis CE, van der Kuur J

Assessment of Fracture Studies on Zircaloy-2 Pressure Tubes
Pickles BW, Cowan A, Johnson ER

Irradiation Damage Recovery in Some Zirconium Alloys
Carpenter GJC, Watters JF

Stress Corrosion Cracking of Zircaloys in Iodine Containing Environments
Cox B

Microstructure of the Oxide Films Formed on Zirconium-Based Alloys
Sabol GP, McDonald SG, Airey GP

Corrosion and Hydriding Performance of Zircaloy Tubing After Extended Exposure in the Shippingport Pressurized Water Reactor
Hillner E

Characterization of Zircaloy Oxidation Films
Urquhart AW, Vermilyea DA

Fracture of Zircaloy-2 in an Environment Containing Iodine
van der Schaaf B

Study of Zirconium Alloy Corrosion Parameters in the Advanced Test Reactor
Johnson AB, LeSurf JE, Proebstle RA

Effect of Surface Treatment on the Irradiation Enhancement of Corrosion of Zircaloy-2 in HBWR
Lunde L, Videm K

Committee: B10
Paper ID: STP551-EB
DOI: 10.1520/STP551-EB

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STP551-EB