STP939

    Zirconium in the Nuclear Industry

    Adamson RB, Van Swam LFP

    Pages: 816

    Published: 1987

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    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

    ISBN-PRINT: 978-0-8031-0935-3

    ASTM International is a member of CrossRef.

    0-8031-0935-0
    978-0-8031-0935-3
    STP939-EB