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SEDL / STP / STP939-EB
Forty papers deal with properties of Zircaloy and to a lesser extent, Zr-2.5-Nb. The majority covers fabrication and physical properties, general corrosion and hydriding, fracture and fatigue, and stress corrosion cracking. Special consideration is given to irradiation growth, Zircaloy cladding behavior under conditions expected in a loss-of-coolant accident, and nodular corrosion.
Table of Contents
Overview
Adamson R., Van Swam L.
Mechanistic Modeling of Zircaloy Deformation and Fracture in Fuel Element Analysis
Nichols F.
Anisotropy in Zircaloy
Picklesimer M.
Zirconium Activities in Europe: 1945–1984
Syre R.
An Overview of Microstructural and Experimental Factors That Affect the Irradiation Growth Behavior of Zirconium Alloys
Adamson R., Fidleris V., Tucker R.
Microstructural Effects on the Irradiation Growth of Zr-2.5Nb
Fleck R., Leger M., Parker J., Perovic V.
Effect of Irradiation at 588 K on Mechanical Properties and Deformation Behavior of Zirconium Alloy Strip
Baicry J., Mardon J., Morize P.
Upper and Lower Bound Crystal Plastic Modelling of Creep Loci of Zircaloy
Adams B., Mahmood S., Murty K.
Discussion
Recycling Off-Grade Zircaloy Scrap Using a Molten-Salt Electro-Refining Process
Chintamani ., Pande P., Saratchandran N., Sehra J., Taneja A.
Influence of Hydrostatic Extrusion on Properties of Zirconium and Zircaloys
Jimei S.
Discussion
Laser Beam Beta Heat Treatment of Zircaloy
Jacobsen W., McDonald S., Nurminen J., Sabol G.
Discussion
Long-Term Corrosion and Deuterium Uptake in CANDU-PHW Pressure Tubes
Cox B., Field G., Urbanic V.
Discussion
Effects of Heat Flux and Irradiation-Induced Changes in Water Chemistry on Zircaloy Nodular Oxidation
Franklin D., Li C.
Discussion
Prevention of Delayed Hydride Cracking in Zirconium Alloys
Ambler J., Cheadle B., Coleman C.
Parametric Study of an Autoclave Test for Nodular Corrosion
Schemel J.
Development of a Sensitive and Reproducible Steam Test for Zircaloy Nodular Corrosion
Adamson R., Cheng B., Levin H., Marlowe M., Monroe V.
Discussion
Influence of Impurities and Temperature on the Microstructure of Zircaloy-2 and Zircaloy-4 after the Beta → Alpha Phase Transformation
Alheritiere E., Charquet D.
Discussion
Influence of Second-Phase Particles on Zircaloy Corrosion in BWR Environment
Massih A., Rudling P., Vannesjö K., Vesterlund G.
Discussion
Nucleation and Growth of Intermetallic Precipitates in Zircaloy-2 and Zircaloy-4 and Correlation to Nodular Corrosion Behavior
Maussner G., Steinberg E., Tenckhoff E.
Nodular Corrosion Resistance of Zircaloy-2 in Relation to Second-Phase Particle Distribution
Andersson T., Thorvaldsson T.
Effect of Beta Quenching on the Microstructure and Corrosion of Zircaloys
Bangaru N., Busch R., Schemel J.
Effect of Chemistry on Elevated Temperature Nodular Corrosion
Baroch E., Eucken C., Garzarolli F., Weidinger H.
Mechanistic Studies of Zircaloy Nodular Corrosion
Adamson R., Cheng B.
Progress in the Knowledge of Nodular Corrosion
Garzarolli F., Stehle H., Steinberg E., Weidinger H.
Influence of Variations in Early Fabrication Steps on Corrosion, Mechanical Properties, and Structure of Zircaloy-4 Products
Charquet D., Millet Y., Steinberg E.
Discussion
Zircaloy Fuel Cladding Behavior in a Loss-of-Coolant Accident: A Review
Erbacher F., Leistikow S.
Oxidation of Zircaloy-4 in Steam at 1300 to 2400°C
Courtright E., Prater J.
Discussion
Experimental and Theoretical Results of Cladding Oxidation Under Severe Fuel-Damage Conditions
Hofmann P., Neitzel H.
Influence of the Initial Material Condition on the Deformation Behavior of Zircaloy Cladding Tubes in the High-α-Phase Region
Cheliotis G., Ortlieb E., Weidinger H.
Discussion
Study by Thermoelectric Power Measurements of Recovery and Recrystallization of Cold-Rolled Zircaloy-4 Sheets
Charquet D., Derep J., Fantozzi G., Merle P., Vauglin C.
Effect of Metallurgical Variables and Temperature on the Fracture Toughness of Zirconium Alloy Pressure Tubes
Chow C., Simpson L.
Cumulative Fatigue and Creep-Fatigue Damage at 350°C on Recrystallized Zircaloy-4
Brun G., Floz J., Galimberti M., Pelchat J.
Cyclic Behavior of Zircaloy-4 at Elevated Temperatures
Alvarez-Armas I., Armas A.
Residual Stresses in Textured Zirconium Alloys
MacEwen S., Tomé C.
Effect of Cold Reduction on Anisotropy of Zircaloy Tubing
Abe H., Honji M., Kojima T., Konishi T.
Discussion
Cold-Rolled and Annealed Textures of Zircaloy-4 Thin Strips
Alheritiere E., Blanc G., Charquet D.
Zirconium-Barrier Cladding Attributes
Adamson R., Armijo J., Cheng B., Davies J., Rand R., Rosenbaum H., Tucker R., Wisner S.
Discussion
Iodine-Induced Stress Corrosion of Zircaloy Fuel Cladding: Initiation and Growth
Brunisholz L., Lemaignan C.
Recent Studies of Crack Initiation During Stress Corrosion Cracking of Zirconium Alloys
Cox B., Haddad R.
Deformation and Fracture Properties of Neutron-Irradiated Recrystallized Zircaloy-2 Cladding under Uniaxial Tension
Nakatsuka M., Yamashita K., Yasuda T.
Chemical Inhomogeneity Populations in Various Zircaloy Claddings and Their Association with SCC and Corrosion Resistance
Brooks M., Cheung T., Miller A., Santucci J., Tasooji A.
Fracture Behavior and Microstructural Characteristics of Irradiated Zircaloy Cladding
Chung H., Kassner T., Yaggee F.
Discussion
Author Index
Subject Index
Committee: B10
Paper ID: STP939-EB
DOI: 10.1520/STP939-EB
ISBN-EB: 978-0-8031-5004-1
 ASTM International is a member of CrossRef.
0-8031-0935-0
978-0-8031-0935-3
STP939-EB
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