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SEDL / STP / STP1505-EB
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STP1505
Zirconium in the Nuclear Industry: 15th International Symposium
Kammenzind Bruce, Limbäck Magnus
Pages: 810
Published: 2009
Other books in this series
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The latest in this popular series provides 44 peer-reviewed papers on the latest international research covering all aspects of zirconium alloy properties and performance relevant to the nuclear industry. Topics address: • All aspects of the fuel cycle • Basic metallurgy • Spent fuel • Corrosion • Mechanical properties • Deformations mechanisms • Failure mechanisms • LOCA and Transients. These papers provide examples of studies where experimental techniques are combined with analytical tools and calculations; reflect a stronger trend towards efforts that enable fundamental in-reactor measurements, which are essential for further development of experimental techniques as well as for the possibility to enhance the development of improved alloys; and examine an increasing number of alternative alloys being developed and verified.
Table of Contents
In-Reactor Deformation of Zirconium Alloy Components
Holt R.
Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence
Griffiths M.
Characterization of Zirconium Hydrides and Phase Field Approach to a Mesoscopic-Scale Modeling of Their Precipitation
Ambard A., Blat-Yrieix M., Kihn Y., Legras L., Legris A., Morniroli J., Thuinet L., Zhao Z.
Influence of Structure Changes in E110 Alloy Claddings on Ductility Loss under LOCA Conditions
Belov V., Lyaschenko N., Mal'gin A., Nikulin S., Nikulina A., Rozhnov A.
Investigations of the Microstructure and Mechanical Properties of Prior-β Structure as a Function of the Oxygen Content in Two Zirconium Alloys
Barcelo F., Brachet J., Hamon D., Lesbros A., Maillot V., Mardon J., Pineau A., Poissonnet S., Stern A.
Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions
Brachet J., Gilbon D., Lesbros A., Mardon J., Portier L., Vandenberghe-Maillot V., Waeckel N.
Experimental and Analytical Investigation of the Mechanical Behavior of High-Burnup Zircaloy-4 Fuel Cladding
Billone M., Daum R., Majumdar S.
Effect of Local Hydride Accumulations on Zircaloy Cladding Mechanical Properties
Gavillet D., Hermann A., Yagnik S.
Fracture Toughness of Hydrided Zircaloy-4 Sheet under through-Thickness Crack Growth Conditions
Chan K., Koss D., Motta A., Raynaud P.
Characterization of Local Strain Distribution in Zircaloy-4 and M5® Alloys
Barberis P., Bornert M., Bretheau T., Crépin J., Doumalin P., Elbachiri K., Rebeyrolle V.
In-Pile Criteria for the Initiation of Massive Hydriding of Zr in Steam-Hydrogen Environment
Evdokimov I., Likhanskii V.
Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing
Adamson R., Bertsch J., Efsing P., Fukuda T., Grigoriev V., Kuo R., Mahmood S., Oberländer B., Ramasubramanian N., Sainte-Catherine C., Yagnik S.
Role of Twinning and Slip in Deformation of a Zr-2.5Nb Tube
Kim Y.
Measurement of Rates of Delayed Hydride Cracking (DHC) in Zr-2.5Nb Alloys—An IAEA Coordinated Research Project
Coleman C., Inozemtsev V.
A Study of the Structure and Chemistry in Zircaloy-2 and the Resulting Oxide After High Temperature Corrosion
Dahlbäck M., Hutchinson B., Lehtinen B., Limbäck M.
Effects of Pt Surface Coverage on Oxidation of Zr and Other Materials
Anghel C., Hultquist G., Limbäch M., Szakalos P.
Studies of Corrosion of Cladding Materials in Simulated BWR Environment using Impedance Measurements
Ahlberg E., Forsberg S., Limbäch M.
In Situ EIS Measurements of Irradiated Zircaloy-4 Post-Transition Corrosion Kinetic Behavior
Eklund K., Kammenzind B., Rishel D.
Effect of Water Chemistry and Composition on Microstructural Evolution of Oxide on Zr Alloys
Chu Y., Li Q., Liu W., Yao M., Zhou B.
The Effect of Hydrogen on the Transition Behavior of the Corrosion Rate of Zirconium Alloys
Harada M., Wakamatsu R.
A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor
Ambard A., Bénier G., Bouineau V., Duverneix T., Fayette L., Godlewski J., Pêcheur D.
In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5® and Recrystallized Low-Tin Zircaloy-4
Blat M., Bossis P., Chabretou V., Dalmais A., Doriot S., Gilbon D., Mardon J., Miquet A., Verhaeghe B.
ZIRLO™ Cladding Improvement
Comstock R., Foster J., Yueh H.
Corrosion and Oxide Properties of HANA Alloys
Choi B., Jeong Y., Park J., Yoo S.
Microstructural Characterization of Oxides Formed on Model Zr Alloys Using Synchrotron Radiation
Cai Z., Comstock R., Gomes da Silva M., Lai B., Motta A., Yilmazbayhan A.
Chemistry of Waterside Oxide Layers on Pressure Tubes
Do T., Hocking W., Saidy M.
Manufacturing Variability, Microstructure, and Deformation of Zr-2.5Nb Pressure Tubes
Bickel G., Griffiths M.
Effect of Irradiation Damage on the Deformation Properties of Zr-2.5Nb Pressure Tubes
Buyers A., Donohue S., Griffiths M., Wang N.
Determination and Interpretation of Texture Evolution during Deformation of a Zirconium Alloy
Allen V., Comstock R., Daymond M., Preuss M., Quinta da Fonseca J., Robson J.
Irradiation-Induced Growth and Microstructure of Recrystallized, Cold Worked and Quenched Zircaloy-2, NSF, and E635 Alloys
Dubecky M., Kobylyansky G., Lin Y., Mahmood S., Nikulina A., Novoselov A., Obukhov A., Ostrovsky Z., Peregud M., Shishin V., Shishov V., White D.
Deformation Anisotropy of Annealed Zircaloy-2 as a Function of Fast Neutron Fluence
Griffiths M., Theaker J., Wei X.
Toward a Better Understanding of Dimensional Changes in Zircaloy-4: What is the Impact Induced by Hydrides and Oxide Layer?
Ambard A., Beguin S., Blat-Yrieix M., Cayet N., Foct F., Miquet A.
CASTA DIVA®: Experiments and Modeling of Oxide-Induced Deformation in Nuclear Components
Barberis P., Chabretou V., Rebeyrolle V., Vassault J., Vermoyal J.
Cladding Tube Deformation Test for Stress Reorientation of Hydrides
Alam A., Hellwig C.
Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage
Aomi M., Baba T., Kamimura K., Miyashita T., Shinohara Y., Takeda T., Yasuda T.
Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress
Béchade J., Barbu A., Cappelaere C., Doriot S., Lemaignan C., Onimus F., Rabouille O., Ribis J.
Mechanical Properties of Zr-2.5Nb Pressure Tubes Made from Electrolytic Powder
Coleman C., Griffiths M., Grigoriev V., Kiseliov V., Markelov V., Rodchenkov B.
Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys
Khokhunova T., Kobylyansky G., Kon'kov V., Markelov V., Nikulina A., Novikov V., Novoselov A., Obukhov A., Ostrovsky Z., Peregud M., Shishov V.
Investigation of Structural and Chemical Uniformity of Zr2.5% Nb and E635 Alloy by Radioactive Indicators
Arzhakova V., Belov V., Kabanov A., Kurapov V., Kurapova L., Shikov A., Shtutsa M., Ziganshin A.
Contribution of Thermodynamic Calculations to Metallurgical Studies of Multi-Component Zirconium Based Alloys
Barberis P., Brachet J., Dupin N., Joubert J., Servant C., Toffolon-Masclet C., Zeller P.
Intergranular and Interphase Constraints in Zirconium Alloys
Cai S., Daymond M., Holt R., Xu F.
Tearing Crack Growth and Fracture Micro-Mechanisms Under Micro Segregation in Zr-2.5%Nb Pressure Tube Material
Kapoor K., Kashyap B., Ramana Rao A., Saibaba N.
Author Index
Subject Index
Committee: B10
Paper ID: STP1505-EB
DOI: 10.1520/STP1505-EB
ISBN-EB: 978-0-8031-8007-9
 ASTM International is a member of CrossRef.
0-8031-4514-4
978-0-8031-4514-6
STP1505-EB
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