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SEDL / STP / STP1467-EB
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STP1467
Zirconium in the Nuclear Industry: Fourteenth International Symposium
Rudling P, Kammenzind B
Pages: 918
Published: 2005
Other books in this series
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Forty-one peer-reviewed papers cover all aspects of the fuel cycle. The Basic Metallurgy and Processing sections represent the beginning of the fuel cycle from component design and manufacture. The BWR Corrosion, PWR Corrosion, and Deformation Mechanism sections represent component performance under nominal service conditions. The Primary Failure Mechanism and the Transient and High Temperature Performance sections cover aspects that might end the useful service life of the component. The remaining papers deal with post service life of the component in a dry storage and in a repository environment.
Table of Contents
ZIRLO™ — An Alloy Development Success
Sabol G.
Review of Deformation Mechanisms, Texture, and Mechanical Anisotropy in Zirconium and Zirconium Base Alloys
Tenckhoff E.
Plastic Deformation of Irradiated Zirconium Alloys: TEM Investigations and Micro-Mechanical Modeling
Béchade J., Doriot S., Gilbon D., Legras L., Mardon J., Monnet I., Onimus F., Pilvin P., Prioul C., Robert L., Verhaeghe B.
Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys
Barberis P., Brachet J., Legras L., Mardon J., Toffolon-Masclet C.
On Secondary β-Nb Phase Precipitation within Primary α-Zr Phase in Zr-Nb Alloys During Tensile Deformation
Kapoor K., Kashyap B., Padmaprabu C., Paul T., Rao M., Rao S., Saibaba N., Sanyal T., Saroja S.
Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects
Barberis P., Dupin N., Grange J., Lemaignan C., Pasturel A.
Modeling of the Simultaneous Evolution of Vacancy and Interstitial Dislocation Loops in hcp Metals Under Irradiation
Abyzov A., Dubinko V., Griffiths M., Turkin A.
Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences
Béchade J., Doriot S., Gilbon D., Legras L., Mardon J., Mathon M.
Microstructure and Growth Mechanism of Oxide Layers Formed on Zr Alloys Studied with Micro-Beam Synchrotron Radiation
Cai Z., Comstock R., Lai B., Motta A., Partezana J., Sabol G., Yilmazbayhan A.
Simulation of Cold Pilgering Process by a Generalized Plane Strain FEM
Honda A., Horada M., Toyoshima S.
Temperature and Strain Rate Effects on Zr-1%Nb Alloy Deformation
Belov V., Bocharov O., Filippov V., Kabanov A., Kotrekhov V., Losistskiy A., Rozhdestvenski V., Shikov A., Zavodchikov S.
Phase Composition, Structure, and Plastic Deformation Localization in Zr1%Nb alloys
Arzhakova V., Belov V., Bocharov O., Cheremnykh G., Filippov V., Poletika T., Shikov A., Zavodchikov S., Zuev L.
The Effect of Beta-Quenching in Final Dimension on the Irradiation Growth of Tubes and Channels
Andersson T., Askeljung P., Barberis P., Bunel G., Dahlbäck M., Flygare J., Hallstadius L., Lehtinen B., Limbäck M., Massih A., Simonot C.
Destruction of Crystallographic Texture in Zirconium Alloy Tubes
Bryk V., Chernyayeva T., Grytsyna V., Krasnorutskyy V., Malykhin D., Stukalov A., Voyevodin V.
Improved ZIRLO™ Cladding Performance through Chemistry and Process Modifications
Colburn D., Comstock R., Dahlback M., Hallstadius L., Kesterson R., Shah H., Yueh H.
Role of Iron for Hydrogen Absorption Mechanism in Zirconium Alloys
Furuya T., Ishii Y., Itagaki N., Kakiuchi K., Miyazaki A., Suzuki S., Terai T., Yamawaki M.
In-Situ Studies of the Oxide Film Properties on BWR Fuel Cladding Materials
Bojinov M., Hansson-Lyyra L., Kinnunen P., Saario T., Sirkiä P.
The Correlation Between Microstructures and in-BWR Corrosion Behavior of Highly Irradiated Zr-based Alloys
Etoh Y., Ishimoto S., Kubo T., Kubota O., Ogata K., Takagawa Y.
Effect of Alloying Elements and Impurities on in-BWR Corrosion of Zirconium Alloys
Garzarolli F., Sell H., Trapp-Pritsching S.
In-Core Tests of Effects of BWR Water Chemistry Impurities on Zircaloy Corrosion
Cheng B., Ibe H., Ichikawa N., Kubota O., Lutz D., Shimada S.
Shadow Corrosion Mechanism of Zircaloy
Lysell G., Nystrand A., Ullberg M.
TEM Examinations of the Metal-Oxide Interface of Zirconium Based Alloys Irradiated in a Pressurized Water Reactor
Abolhassani S., Aeschbach F., Bart G., Goll W., Groeschel F., Hoffelner W., Rebac T., Restani R.
Comparison of the High Burn-Up Corrosion on M5 and Low Tin Zircaloy-4
Blat M., Bossis P., Hanifi K., Pêcheur D., Thomazet J.
The Effect of Duplex Cladding Outer Component Tin Content on Corrosion, Hydrogen Pick-up, and Hydride Distribution at Very High Burnup
Andersson T., Arborelius J., Dahlbäck M., Hahn M., Hallstadius L., Jourdain P., Lisdat R., Toscano E.
Predicting Oxidation and Deuterium Ingress for Zr-2.5Nb CANDU Pressure Tubes
Bahurmuz A., Muir I., Urbanic V.
Inhibitors for Reducing Hydrogen Ingress During Corrosion of Zirconium Alloys
Donner A., Elmoselhi M.
Identification of Crystalline Behavior on Macroscopic Response and Local Strain Field Analysis: Application to Alpha Zirconium Alloys
Crépin J., Dexet M., Gélébart L., Roos A., Sauzay M.
Ductility of Zircaloy-4 Fuel Cladding and Guide Tubes at High Fluences
Hermann A., Kuo R., Yagnik S.
Thermal Creep of Irradiated Zircaloy Cladding
Billone M., Tsai H.
Use of the Irradiation-Thermal Creep Model of Zr-1 % Nb Alloy Cladding Tubes to Describe Dimensional Changes of VVER Fuel Rods
Kanashov B., Nuzhdov A., Polenok V., Rogozyanov A., Smirnov A.
Influence of Structure—Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth
Kobylyansky G., Nikulina A., Novoselov A., Obukhov A., Ostrovsky Z., Peregud M., Pimenov Y., Shishov V.
Damage Dependence of Irradiation Deformation of Zr-2.5Nb Pressure Tubes
Christodoulou N., Donohue S., Griffiths M.
Delayed Hydrogen Cracking Velocity and J-Integral Measurements on Irradiated BWR Cladding
Grigoriev V., Jakobsson R.
Overload Fracture of Flaw Tip Hydrides in Zr-2.5Nb Pressure Tubes
Cui J., Perovic V., Shek G.
Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life
Davies P., Griffiths M., Pan Z., Sagat S., St Lawrence S.
Effect of Fabrication Variables on Irradiation Response of Crack Growth Resistance of Zr-2.5Nb
Coleman C., Kidd K., Theaker J.
Fretting-Wear Behavior of Zircaloy-4, OPTIN™, and ZIRLO™ Fuel Rods and Grid Supports under Various Autoclave and Hydraulic Loop Endurance Test Conditions
Fisher N., Guérout F., King S., Young M.
Failure of Hydrided Zircaloy-4 Under Equal-Biaxial and Plane-Strain Tensile Deformation
Damt R., Glendening A., Koss D., Motta A., Pierron O.
Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior
Averty X., Bernaudat C., Cazalis B., Desquines J., Poussard C., Yvon P.
The Effect of Liner Component Iron Content on Cladding Corrosion, Hydriding, and PCI Resistance
Alvarez A., Andersson T., Díaz M., Dahlbäck M., Engman U., Hallstadius L., Izquierdo J., Jakobsson R., Limbäck M., Massih A., Remartinez B., Sacedon J., Vesterlund G., Witt P.
Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions
Brachet J., Bredel T., Lesbros A., Maillot V., Mardon J., Portier L.
Author Index
Subject Index
Committee: B10
Paper ID: STP1467-EB
DOI: 10.1520/STP1467-EB
ISBN-EB: 978-0-8031-5519-0
 ASTM International is a member of CrossRef.
0-8031-3493-2
978-0-8031-3493-5
STP1467-EB
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