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SEDL / STP / STP1023-EB
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STP1023
Zirconium in the Nuclear Industry: Eighth International Symposium
Eucken CM, Van Swam LFP
Pages: 756
Published: 1989
Other books in this series
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Topics include: • Behavior of Pressure Tubes • Corrosion • Nodular Corrosion • Basic Metallurgy • Mechanical Behavior, Stress Corrosion, and Fatigue • Creep and Growth Corrosion behavior is given special emphasis.
Table of Contents
Corrosion and Hydriding of N Reactor Pressure Tubes
Boyd S., Johnson A., Lanning D., Trimble D.
Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW Reactors
Chow C., Manolescu A., Shanahan M., Urbanic V., Warr B.
Evaluation of Zircaloy-2 Pressure Tubes from NPD
Causey A., Cheadle B., Chow P., Coleman C., Davies P., McManus M., Rodgers D., Sagat S., van Drunen G.
Growth, Fracture, and Nondestructive Evaluation of Hydride Blisters in Zr-2.5 Nb Pressure Tubes
Leger M., Moan G., Wallace A., Watson N.
Effects of Hydride Morphology on Zr-2.5Nb Fracture Toughness
Lepik O., Shek G., Wallace A.
Effects of Loading and Thermal Maneuvers on Delayed Hydride Cracking in Zr-2.5 Nb Alloys
Graham D., Shek G.
Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests
Eucken C., Finden P., Trapp-Pritsching S., Weidinger H.
Correlation Between 400°C Steam Corrosion Behavior, Heat Treatment, and Microstructure of Zircaloy-4 Tubing
Andersson T., Thorvaldsson T., Wardle A., Wilson A.
Influence of the Manufacturing Process on the Corrosion Resistance of Zircaloy-4 Cladding
Charquet D., Schemel J., Wadier J.
A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under Irradiation
Gerber F., Johnson A., Lanning D., Levy I., Trimble D.
Development of a Mechanistic Model to Assess the External Corrosion of the Zircaloy Claddings in PWRs
Beslu P., Billot P., Giordano A., Thomazet J.
Lithium Uptake and the Accelerated Corrosion of Zirconium Alloys
Ling V., Precoanin N., Ramasubramanian N.
Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding
Garzarolli F., Steinberg E., Weidinger H.
Corrosion Performance of Zircaloy-2 and Zircaloy-4 PWR Fuel Cladding
Andersson T., Pettersson H., Rudling P., Thorvaldsson T.
Development of a Cladding Alloy for High Burnup
Balfour M., Kilp G., Roberts E., Sabol G.
Enhanced Low-Temperature Oxidation of Zirconium Alloys Under Irradiation
Cox B., Fidleris V.
Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods
Clayton J.
A Systematic Survey of the Factors Affecting Zircaloy Nodular Corrosion
Abe K., Aoki T., Fujibayashi T., Hattori T., Inagaki M., Kodama T., Murota K., Ogata K., Okubo T., Yoshitsugu M.
Corrosion Performance Ranking of Zircaloy-2 for BWR Applications
Machiels A., Rudling P.
Influence of Chemical Composition and Manufacturing Variables on Autoclave Corrosion of the Zircaloys
Finden P., Graham R., Tosdale J.
Effects of Alloying Element Distribution on the Nodular Corrosion of Zircaloy-2
Ogata K.
Electron Microscopy Study of Oxide Films Formed on Zircaloy-2 in Superheated Steam
Zhou B.
Heterogeneous Scale Growth During Steam Corrosion of Zircaloy-4 and 500°C
Charquet D., Tricot R., Wadier J.
Automatic System for Measuring the Zirconium Liner and Zircaloy-2 Thickness of Zirconium Liner Tubes
Honji M., Hyodo S., Morimoto Y., Sakamoto T.
Solubility Limits and Formation of Intermetallic Precipitates in ZrSnFeCr Alloys
Charquet D., Gros J., Hahn R., Ortlieb E., Wadier J.
Direct Measurement of Matrix Composition in Zircaloy-4 by Atom Probe Microanalysis
Andrén H., Wadman B.
Beta-Quenched Zircaloy-4: Effects of Thermal Aging and Neutron Irradiation
Adamson R., Yang W.
Intermetallic Precipitates in Zirconium-Niobium Alloys
Meng X., Northwood D.
Magnetic Study of Zircaloy
Miyake C., Takamiya T.
Oxidation Kinetics and Auger Microprobe Analysis of Some Oxidized Zirconium Alloys
Ploc R.
Simulated Fuel Expansion Testing of Zircaloy Tubing
Foster J., Leasure R.
Link Between Stress Corrosion and Corrosion-Fatigue Behavior of Zircaloy in an Iodine Environment
Lemaignan C., Schuster I.
Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High Fluence
Garde A.
Applications of Crystallographic Textures of Zirconium Alloys in the Nuclear Industry
Murty K.
Stress Versus Strain Rate Characteristics of Zircaloy Cladding Tubes Subjected to Various Deformation Paths
Okubo T., Suzuki H.
The Influence of Tin Content on the Thermal Creep of Zircaloy-4
Baty D., McInteer W., Stein K.
Effects of High Neutron Fluences on Microstructure and Growth of Zircaloy-4
Basso H., Dewes P., Garzarolli F., Maussner G.
Accelerated Irradiation Growth of Zirconium Alloys
Fidleris V., Gilbert R., Griffiths M.
Creep Behavior of Zircaloy Cladding Under Variable Conditions
Matsuo Y.
Effects of Microstructural Factors on Irradiation Growth in Zirconium-Niobium Alloys
Fuse M., Sadaoka N.
The Effect of Temperature on the Irradiation Growth of Cold-Worked Zr-2.5 Nb
Fleck R., Holt R.
Discussion Section
Author Index
Subject Index
Committee: B10
Paper ID: STP1023-EB
DOI: 10.1520/STP1023-EB
ISBN-EB: 978-0-8031-5084-3
 ASTM International is a member of CrossRef.
0-8031-1199-1
978-0-8031-1199-8
STP1023-EB
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