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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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Table of Contents

Overview PDF

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
Onimus F., Béchade J., Prioul C., Pilvin P., Monnet I., Doriot S., Verhaeghe B., Gilbon D., Robert L., Legras L., Mardon J.

Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys
Toffolon-Masclet C., Barberis P., Brachet J., Mardon J., Legras L.

On Secondary β-Nb Phase Precipitation within Primary α-Zr Phase in Zr-Nb Alloys During Tensile Deformation
Kapoor K., Padmaprabu C., Saroja S., Paul T., Rao S., Sanyal T., Rao M., Saibaba N., Kashyap B.

Microstructure and Phase Control in Zr-Fe-Cr-Ni Alloys: Thermodynamic and Kinetic Aspects
Barberis P., Dupin N., Lemaignan C., Pasturel A., Grange J.

Modeling of the Simultaneous Evolution of Vacancy and Interstitial Dislocation Loops in hcp Metals Under Irradiation
Dubinko V., Turkin A., Abyzov A., Griffiths M.

Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences
Doriot S., Gilbon D., Béchade J., Mathon M., Legras L., Mardon J.

Microstructure and Growth Mechanism of Oxide Layers Formed on Zr Alloys Studied with Micro-Beam Synchrotron Radiation
Motta A., Yilmazbayhan A., Comstock R., Partezana J., Sabol G., Lai B., Cai Z.

Simulation of Cold Pilgering Process by a Generalized Plane Strain FEM
Horada M., Honda A., Toyoshima S.

Temperature and Strain Rate Effects on Zr-1%Nb Alloy Deformation
Bocharov O., Zavodchikov S., Belov V., Kabanov A., Kotrekhov V., Rozhdestvenski V., Filippov V., Losistskiy A., Shikov A.

Phase Composition, Structure, and Plastic Deformation Localization in Zr1%Nb alloys
Zuev L., Zavodchikov S., Poletika T., Cheremnykh G., Filippov V., Belov V., Arzhakova V., Bocharov O., Shikov A.

The Effect of Beta-Quenching in Final Dimension on the Irradiation Growth of Tubes and Channels
Dahlbäck M., Limbäck M., Hallstadius L., Barberis P., Bunel G., Simonot C., Andersson T., Askeljung P., Flygare J., Lehtinen B., Massih A.

Destruction of Crystallographic Texture in Zirconium Alloy Tubes
Grytsyna V., Stukalov A., Chernyayeva T., Krasnorutskyy V., Malykhin D., Voyevodin V., Bryk V.

Improved ZIRLO™ Cladding Performance through Chemistry and Process Modifications
Yueh H., Kesterson R., Comstock R., Shah H., Colburn D., Dahlback M., Hallstadius L.

Role of Iron for Hydrogen Absorption Mechanism in Zirconium Alloys
Kakiuchi K., Itagaki N., Furuya T., Miyazaki A., Ishii Y., 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
Takagawa Y., Ishimoto S., Etoh Y., Kubo T., Ogata K., Kubota O.

Effect of Alloying Elements and Impurities on in-BWR Corrosion of Zirconium Alloys
Sell H., Trapp-Pritsching S., Garzarolli F.

In-Core Tests of Effects of BWR Water Chemistry Impurities on Zircaloy Corrosion
Shimada S., Cheng B., Lutz D., Kubota O., Ichikawa N., Ibe H.

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., Restani R., Rebac T., Groeschel F., Hoffelner W., Bart G., Goll W., Aeschbach F.

Comparison of the High Burn-Up Corrosion on M5 and Low Tin Zircaloy-4
Bossis P., Pêcheur D., Hanifi K., Thomazet J., Blat M.

The Effect of Duplex Cladding Outer Component Tin Content on Corrosion, Hydrogen Pick-up, and Hydride Distribution at Very High Burnup
Arborelius J., Dahlbäck M., Hallstadius L., Jourdain P., Andersson T., Lisdat R., Hahn M., 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
Elmoselhi M., Donner A.

Identification of Crystalline Behavior on Macroscopic Response and Local Strain Field Analysis: Application to Alpha Zirconium Alloys
Gélébart L., Crépin J., Dexet M., Sauzay M., Roos A.

Ductility of Zircaloy-4 Fuel Cladding and Guide Tubes at High Fluences
Yagnik S., Hermann A., Kuo R.

Thermal Creep of Irradiated Zircaloy Cladding
Tsai H., Billone M.

Use of the Irradiation-Thermal Creep Model of Zr-1 % Nb Alloy Cladding Tubes to Describe Dimensional Changes of VVER Fuel Rods
Rogozyanov A., Smirnov A., Kanashov B., Polenok V., Nuzhdov A.

Influence of Structure-Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth
Shishov V., Peregud M., Nikulina A., Pimenov Y., Kobylyansky G., Novoselov A., Ostrovsky Z., Obukhov A.

Damage Dependence of Irradiation Deformation of Zr-2.5Nb Pressure Tubes
Griffiths M., Christodoulou N., Donohue S.

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
Shek G., Cui J., Perovic V.

Effect of Irradiation on the Fracture Properties of Zr-2.5Nb Pressure Tubes at the End of Design Life
Pan Z., St Lawrence S., Davies P., Griffiths M., Sagat S.

Effect of Fabrication Variables on Irradiation Response of Crack Growth Resistance of Zr-2.5Nb
Coleman C., Theaker J., Kidd K.

Fretting-Wear Behavior of Zircaloy-4, OPTIN™, and ZIRLO™ Fuel Rods and Grid Supports under Various Autoclave and Hydraulic Loop Endurance Test Conditions
King S., Young M., Guérout F., Fisher N.

Failure of Hydrided Zircaloy-4 Under Equal-Biaxial and Plane-Strain Tensile Deformation
Glendening A., Koss D., Motta A., Pierron O., Damt R.

Mechanical Properties of Zircaloy-4 PWR Fuel Cladding with Burnup 54-64MWd/kgU and Implications for RIA Behavior
Desquines J., Cazalis B., Bernaudat C., Poussard C., Averty X., Yvon P.

The Effect of Liner Component Iron Content on Cladding Corrosion, Hydriding, and PCI Resistance
Dahlbäck M., Hallstadius L., Limbäck M., Vesterlund G., Andersson T., Witt P., Izquierdo J., Remartinez B., Díaz M., Sacedon J., Alvarez A., Engman U., Jakobsson R., Massih A.

Influence of Long Service Exposures on the Thermal-Mechanical Behavior of Zy-4 and M5™ Alloys in LOCA Conditions
Portier L., Bredel T., Brachet J., Maillot V., Mardon J., Lesbros A.

Author Index


Subject Index


Committee: B10
Paper ID: STP1467-EB
DOI: 10.1520/STP1467-EB
ISBN-EB: 978-0-8031-5519-0

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STP1467-EB