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