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SEDL / STP / STP824-EB
Discusses zirconium extraction and reduction to tubes; recent work on basic properties; fracture properties, including stress-corrosion cracking and hydrogen cracking; high-temperature properties; texture-related work with special interest in creep and growth; and waterside corrosion.
Table of Contents
Introduction
Franklin D., Adamson R.
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Summary
Adamson R., Franklin D.
Extractive Metallurgy of Zirconium—1945 to the Present
Stephens W.
New Process for Zirconium and Hafnium Separation
Moulin L., Thouvenin P., Brun P.
New Solvent Extraction Process for Zirconium and Hafnium
Takahashi M., Miyazaki H., Katoh Y.
Electron-Beam Remelting of Zircaloys
Mitchell A., Brown R.
Characteristics of Hydrostatically Extruded Zr-2.5Nb Alloy
Jie Z., Zhenhe L., Wenxian H., Yunxia Z., Jiaqi D., Yan L., Tieqi Y.
Pressure Tube Development for CANDU Reactors
Fleck R., Price E., Cheadle B.
Analytical Approaches and Experimental Verification to Describe the Influence of Cold Work and Heat Treatment on the Mechanical Properties of Zircaloy Cladding Tubes
Steinberg E., Weidinger H., Schaa A.
On-Line Ultrasonic Inside-Diameter Control System for Zircaloy Tube Etching
Tanaka Y., Komatsu M., Fujii N., Kubota H.
Variation in the Strain Anisotropy of Zircaloy with Temperature and Strain
Hindle E., Worswick D.
A Study on the Nonelastic Behavior of Zircaloy Fuel Cladding
Suzuki H., Okubo T.
Flow Softening and Anneal Hardening in Two-Phase Zr-2.5Nb
Rizkalla A., Choubey R., Jonas J.
On the Short-Time Recrystallization of Zircaloy-4 Above 600°C
Bäro G., Wessjohann H., Nicoll A.
Orientation of Hydrides in Zirconium Alloy Tubes
Cheadle B., Coleman C., Ipohorski M.
Correlation Between Fabrication Parameters, Microstructure, and Texture in Zircaloy Tubing
Moulin L., Reschke S., Tenckhoff E.
On the Texture Measurements for Zircaloy Cladding Tube
Kimpara M., Fujita K., Kakuma T., Nagai N.
Texture Effect of Zircaloy on Ultrasonic Velocity
Konishi T., Honji M.
In-Reactor Creep of Zr-2.5Nb
Causey A., Holt R., MacEwen S.
Influence of Metallurgical Condition on the In-Reactor Dimensional Changes of Zircaloy Fuel Rods
Garde A., Smerd P., Garzarolli F., Manzel R.
Deformation Characteristics of Cold-Worked and Recrystallized Zircaloy-4 Cladding
Baty D., Pavinich W., Dietrich M., Clevinger G., Papazoglou T.
Irradiation Creep and Growth During Proton and Neutron Bombardment of Zircaloy-2 Plate
Chapman O., McElroy R., Sheldon B.
Irradiation Growth of Annealed Zircaloy-2
Williams J., Darby E., Minty D.
Irradiation-Induced Dimensional Changes in Polycrystalline Iodide Zirconium and Zircaloy-2
Rogerson A.
Irradiation Growth in Zr-2.5Nb
Léger M., Fleck R.
High-Fluence Irradiation Growth of Zirconium Alloys at 644 to 725 K
Tucker R., Fidleris V., Adamson R.
Irradiation Growth of Zircaloy (LWBR Development Program)
Willard H.
Characterization of ZrO2 Films Formed In-Reactor and Ex-Reactor to Study the Factors Contributing to the In-Reactor Waterside Corrosion of Zircaloy
Stehle H., Garzarolli F., Garde A., Smerd P.
Improved Characterization of Aqueous Corrosion Kinetics of Zircaloy-4
Peters H.
Effect of Lithium Hydroxide on the Corrosion Behavior of Zircaloy-4
McDonald S., Sabol G., Sheppard K.
Application of Alternating-Current Impedance Measurements to Characterize Zirconium Alloy Oxidation Films
Rosecrans P.
Observations of Accelerated Hydriding in Zirconium Alloys
Urbanic V.
Out-of-Pile Nickel Alloy-Induced Accelerated Hydriding of Zircaloy Fasteners
Clayton J.
Modeling of Zircaloy Stress-Corrosion Cracking: Texture Effects and Dry Storage Spent Fuel Behavior
Tasooji A., Einziger R., Miller A.
Influence of Crystallographic Texture and Test Temperature on Initiation and Propagation of Iodine Stress-Corrosion Cracks in Zircaloy
Knorr D., Peltier J., Pelloux R.
Effect of Direction of Approach to Temperature on the Delayed Hydrogen Cracking Behavior of Cold-Worked Zr-2.5Nb
Ambler J.
Cracking Zirconium Alloys in Hydrogen
Coleman C., Cox B.
Effect of Bundle Size on Cladding Deformation in LOCA Simulation Tests
Chapman R., Crowley J., Longest A.
Deformation and Failure of Zircaloy Fuel Sheaths Under LOCA Conditions
Sagat S., Sills H., Walsworth J.
Estimation of Conservatism of Present Embrittlement Criteria for Zircaloy Fuel Cladding Under LOCA
Furuta T., Uetsuka H., Kawasaki S.
Out-of-Pile Experiments on the High-Temperature Behavior of Zircaloy-4 Clad Fuel Rods
Hagen S.
Comparison of High-Temperature Steam Oxidation Kinetics Under LWR Accident Conditions: Zircaloy-4 Versus Austenitic Stainless Steel No. 1.4970
Leistikow S.
Fuel Rod Deformation in LOCA and Severe Core Damage Accidents
Burman D., Davis D., Hochreiter L., Lutz R.
High-Temperature Oxidation of Zircaloy in Hydrogen-Steam Mixtures
Chung H., Thomas G.
Physical and Chemical Phenomena Associated with the Dissolution of Solid UO2 by Molten Zircaloy-4
Hofmann P., Kerwin-Peck D., Nikolopoulos P.
Index
Committee: B10
Paper ID: STP824-EB
DOI: 10.1520/STP824-EB
ISBN-EB: 978-0-8031-4895-6
 ASTM International is a member of CrossRef.
0-8031-0270-4
978-0-8031-0270-5
STP824-EB
STP 824
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