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Digital Library / STP / STP1132-EB
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Zirconium in the Nuclear Industry: Ninth International Symposium
Eucken CM
Pages: 787
Published: 1991
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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 DG, Lang PM
Deformability of Zirconium-Lined Cladding Tube in Cold Pilgering
Abe H, Tarui H, Kobayashi T, Honji M, Konishi T
Processing Map and Hot Working Characteristics of Zircaloy-2
Chakravartty JK, Prasad YVRK, Asundi MK
Establishing Statistical Models of Manufacturing Parameters: Zircaloy-4 Cladding Tube Properties
Senevat J, Pape JL, Deshayes J-F
Texture Control in Zircaloy Tubing Through Processing
Cook CS, Sabol GP, Sekera KR, Randall SN
Fracture Toughness Evaluation of Heat-Treated Zr-2.5Nb Pressure Tubes
Asada T, Kimoto H, Chiba N, Kasai Y
Effect of Tensile Deformation on Crystallographic Texture in Zircaloy Sheet
Mahmood ST, Murty KL
Correlation of Microstructure and Mechanical Properties of Zr-Sn Alloys
Wadekar SL, Banerjee S, Raman VV, Asundi MK
Microstructure of Zr-2.5Nb Alloy Pressure Tubing
Northwood DO, Meng-Burany X, Warr BD
Growth in Zircaloy-4 Fuel Clad Arising from Oxidation at Temperatures in the Range 623 to 723 K
Donaldson AT
Effects of Recrystallization and Neutron Irradiation on Creep Anisotropy of Zircaloy Cladding
Murty KL, Mahmood ST
The Contribution of Irradiation Growth to Pressure Tube Deformation
Holt RA, Fleck RG
Fatigue Behavior of Neutron Irradiated Zircaloy-2 Fuel Cladding Tubes
Nakatsuka M, Kubo T, Hayashi Y
Fracture Toughness of Irradiated Zr-2.5Nb Pressure Tubes from CANDU Reactors
Chow CK, Coleman CE, Hosbons RR, Davies PH, Griffiths M, Choubey R
Controlled Composition Zircaloy-2 Uniform Corrosion Resistance
Graham RA, Eucken CM
Influence of Alloy Composition and Processing on the Nodular Corrosion Resistance of Zircaloy-2
Bradley ER, Schemel JH, Nystöm A-L
Investigation of Nodular Corrosion Mechanism for Zircaloy Products
Wang CT, Eucken CM, Graham RA
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
Harada M, Kimpara M, Abe K
Oxide Growth Mechanism on Zirconium Alloys
Garzarolli F, Seidel H, Tricot R, Gros JP
Raman Spectroscopy Study of the Tetragonal-to-monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of O
Godlewski J, Gros JP, Lambertin M, Wadier JF, 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
Wadman B, Andrén H-O
Precipitate Behavior in Zircaloy-2 Oxide Films and Its Relevance to Corrosion Resistance
Kubo T, Uno M
Corrosion-Electrochemical Properties of Zirconium Intermetallics
Weidinger HG, Ruhmann H, Cheliotis G, Maguire M, Yau T-L
Comparison of Zircaloy Corrosion Models from the Evaluation of In-Reactor and Out-of-Pile Loop Performance
Billot Ph, Giordano A
Enhancement of Aqueous Corrosion of Zircaloy-4 Due to Hydride Precipitation at the Metal-Oxide Interface
Garde AM
Corrosion of Zircaloy in the Presence of LiOH
Perkins RA, Busch RA
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 IL, Parsons PD, Tice DR
Effects Of LiOH on Pretransition Zirconium Oxide Films
Cox B, Wong Y-M
Investigation of Variables That Influence Corrosion of Zirconium Alloys during Irradiation
Urbanic VF, Choubey R, Chow CK
Characteristics of Autoclave and In-Reactor Nodular Corrosion of Zircaloys
Jeong YH, Rheem KS, Chung HM
Amorphization of Precipitates in Zircaloy under Neutron and Charged-Particle Irradiation
Motta AT, Lefebvre F, Lemaignan C
Oxide Characteristics and Their Relationship to Hydrogen Uptake in Zirconium Alloys
Warr BD, Elmoselhi MB, Newcomb SB, McIntyre NS, Brennenstuhl AM, Lichtenberger PC
The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water Reactors
Van Swam LFP, Shann SH
Author Index
Subject Index
Committee: B10
Paper ID: STP1132-EB
DOI: 10.1520/STP1132-EB
 ASTM International is a member of CrossRef.
0-8031-1463-X
978-0-8031-1463-0
STP1132-EB
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