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SEDL / STP / STP1132-EB
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STP1132
Zirconium in the Nuclear Industry: Ninth International Symposium
Eucken CM, Garde AM
Pages: 787
Published: 1991
Other books in this series
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36 papers from the most significant body of technical literature on zirconium alloy properties. Sections include: Fabrication, Mechanical Properties, and Corrosion.
Table of Contents
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Zirconium-Alloy Corrosion: A Review Based on an International Atomic Energy Agency (IAEA) Meeting
Franklin D., Lang P.
Deformability of Zirconium-Lined Cladding Tube in Cold Pilgering
Abe H., Honji M., Kobayashi T., Konishi T., Tarui H.
Processing Map and Hot Working Characteristics of Zircaloy-2
Asundi M., Chakravartty J., Prasad Y.
Establishing Statistical Models of Manufacturing Parameters: Zircaloy-4 Cladding Tube Properties
Deshayes J., Pape J., Senevat J.
Texture Control in Zircaloy Tubing Through Processing
Cook C., Randall S., Sabol G., Sekera K.
Fracture Toughness Evaluation of Heat-Treated Zr-2.5Nb Pressure Tubes
Asada T., Chiba N., Kasai Y., Kimoto H.
Effect of Tensile Deformation on Crystallographic Texture in Zircaloy Sheet
Mahmood S., Murty K.
Correlation of Microstructure and Mechanical Properties of Zr-Sn Alloys
Asundi M., Banerjee S., Raman V., Wadekar S.
Microstructure of Zr-2.5Nb Alloy Pressure Tubing
Meng-Burany X., Northwood D., Warr B.
Growth in Zircaloy-4 Fuel Clad Arising from Oxidation at Temperatures in the Range 623 to 723 K
Donaldson A.
Effects of Recrystallization and Neutron Irradiation on Creep Anisotropy of Zircaloy Cladding
Mahmood S., Murty K.
The Contribution of Irradiation Growth to Pressure Tube Deformation
Fleck R., Holt R.
Fatigue Behavior of Neutron Irradiated Zircaloy-2 Fuel Cladding Tubes
Hayashi Y., Kubo T., Nakatsuka M.
Fracture Toughness of Irradiated Zr-2.5Nb Pressure Tubes from CANDU Reactors
Choubey R., Chow C., Coleman C., Davies P., Griffiths M., Hosbons R.
Controlled Composition Zircaloy-2 Uniform Corrosion Resistance
Eucken C., Graham R.
Influence of Alloy Composition and Processing on the Nodular Corrosion Resistance of Zircaloy-2
Bradley E., Nystöm A., Schemel J.
Investigation of Nodular Corrosion Mechanism for Zircaloy Products
Eucken C., Graham R., Wang C.
Development of Highly Corrosion Resistant Zirconium-Base Alloys
Isobe T., Matsuo Y.
Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-based Alloys in 360°C Water and 400°C Steam
Abe K., Harada M., Kimpara M.
Oxide Growth Mechanism on Zirconium Alloys
Garzarolli F., Gros J., Seidel H., Tricot R.
Raman Spectroscopy Study of the Tetragonal-to-monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of O18
Godlewski J., Gros J., Lambertin M., Wadier J., Weidinger H.
Effect of Alloying Elements in Zircaloy on Photo-Electrochemical Characteristics of Zirconium Oxide Films
Inagaki M., Kanno M., Maki H.
Microanalysis of the Matrix and the Oxide-Metal Interface of Uniformly Corroded Zircaloy
Andrén H., Wadman B.
Precipitate Behavior in Zircaloy-2 Oxide Films and Its Relevance to Corrosion Resistance
Kubo T., Uno M.
Corrosion-Electrochemical Properties of Zirconium Intermetallics
Cheliotis G., Maguire M., Ruhmann H., Weidinger H., Yau T.
Comparison of Zircaloy Corrosion Models from the Evaluation of In-Reactor and Out-of-Pile Loop Performance
Billot P., Giordano A.
Enhancement of Aqueous Corrosion of Zircaloy-4 Due to Hydride Precipitation at the Metal-Oxide Interface
Garde A.
Corrosion of Zircaloy in the Presence of LiOH
Busch R., Perkins R.
Lithium Uptake and the Corrosion of Zirconium Alloys in Aqueous Lithium Hydroxide Solutions
Ramasubramanian N.
Corrosion of Zircaloy-4 Pwr Fuel Cladding in Lithiated and Borated Water Environments
Bramwell I., Parsons P., Tice D.
Effects Of LiOH on Pretransition Zirconium Oxide Films
Cox B., Wong Y.
Investigation of Variables That Influence Corrosion of Zirconium Alloys during Irradiation
Choubey R., Chow C., Urbanic V.
Characteristics of Autoclave and In-Reactor Nodular Corrosion of Zircaloys
Chung H., Jeong Y., Rheem K.
Amorphization of Precipitates in Zircaloy under Neutron and Charged-Particle Irradiation
Lefebvre F., Lemaignan C., Motta A.
Oxide Characteristics and Their Relationship to Hydrogen Uptake in Zirconium Alloys
Brennenstuhl A., Elmoselhi M., Lichtenberger P., McIntyre N., Newcomb S., Warr B.
The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water Reactors
Shann S., Van Swam L.
Appendix: List of Poster Presenations
Author Index
Subject Index
Committee: B10
Paper ID: STP1132-EB
DOI: 10.1520/STP1132-EB
ISBN-EB: 978-0-8031-5177-2
 ASTM International is a member of CrossRef.
0-8031-1463-X
978-0-8031-1463-0
STP1132-EB
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