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SEDL / STP / STP1529-EB
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STP1529
Zirconium in the Nuclear Industry: 16th International Symposium
Limbäck Magnus, Barbéris Pierre
Pages: 1087
Published: 2012
Other books in this series
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Forty-two peer-reviewed papers cover the entire spectrum of zirconium metallurgy, from basic metallurgy to accidental conditions and transport, through fabrication, creep and growth, and corrosion and hydriding. Sections cover:
• Kroll Award Papers on explosion cladding; zirconium alloys in light water reactors; and much more.
• Schemel Award Paper on photoelectrochemical investigation of radiation enhanced shadow corrosion phenomenon
• Basic Metallurgy
• Fabrication and Mechanical Properties
• Hydriding—Hydrogen Effect
• Corrosion—Oxide Layer Characterization
• In Pile Behavior
• Creep and Deformation
• Failure Mechanisms and Transients
Table of Contents
Explosion Cladding: An Enabling Technology for Zirconium in the Chemical Process Industry
Banker J.
Performance of Zirconium Alloys in Light Water Reactors with a Review of Nodular Corrosion
Franklin D.
The Evolution of Microstructure and Deformation Stability in Zr-Nb-(Sn,Fe) Alloys Under Neutron Irradiation
Shishov V.
The Development of Zr-2.5Nb Pressure Tubes for CANDU Reactors
Cheadle B.
Photoelectrochemical Investigation of Radiation-Enhanced Shadow Corrosion Phenomenon
Cheng B., Crawford D., Kim Y., Kucuk A., Lin Y., Lutz D., Rebak R.
Dynamic Recrystallization in Zirconium Alloys
Banerjee S., Chakravartty J., Kapoor R., Sarkar A.
Measurement and Modeling of Second Phase Precipitation Kinetics in Zirconium Niobium Alloys
Ivermark M., Preuss M., Robson J.
Texture Evolution of Zircaloy-2 During Beta-Quenching: Effect of Process Variables
Comstock R., Dahlbäck M., Hallstadius L., Preuss M., Quinta da Fonseca J., Romero J.
In Situ Studies of Variant Selection During the α—β—α Phase Transformation in Zr-2.5Nb
Daymond M., Holt R., Mosbrucker P.
Segregation in Vacuum Arc Remelted Zirconium Alloy Ingots
Combeau H., Guerin P., Jardy A., Leclerc F., Rebeyrolle V., Revil-Baudard M.
Damage Build-Up in Zirconium Alloys During Mechanical Processing: Application to Cold Pilgering
Barberis P., Gaillac A., Lemaignan C.
Multiscale Analysis of Viscoplastic Behavior of Recrystallized Zircaloy-4 at 400°C
Cloué J., Feaugas X., Pilvin P., Poquillon D., Priser M., Rautenberg M.
Polycrystalline Modeling of the Effect of Texture and Dislocation Microstructure on Anisotropic Thermal Creep of Pressurized Zr-2.5Nb Tubes
Holt R., Li W., Tracy S.
Improved Zr-2.5Nb Pressure Tubes for Reduced Diametral Strain in Advanced CANDU Reactors
Bickel G., Buyers A., Douchant A., Douglas S., Griffiths M., Woo O.
Microstructural Studies of Heat Treated Zr-2.5Nb Alloy for Pressure Tube Applications
Anantharaman S., Deshmukh V., Dey G., Jha S., Kulkarni R., Mani Krishna K., Neogy S., Ramadasan E., Ramana Rao S., Rath B., Saibaba N., Srivastava D., Tonpe S., Vaibhaw K.
High Temperature Aqueous Corrosion and Deuterium Uptake of Coupons Prepared from the Front and Back Ends of Zr-2.5Nb Pressure Tubes
Bergin S., Elliot A., Nordin H.
Hydrogen Absorption Mechanism of Zirconium Alloys Based on Characterization of Oxide Layer
Aomi M., Etoh Y., Ito K., Kobayashi T., Matsunaga J., Miyamura S., Sakamoto K., Takagi I., Une K.
In Situ Scanning Electron Microscope Observation and Finite Element Method Analysis of Delayed Hydride Cracking Propagation in Zircaloy-2 Fuel Cladding Tubes
Kubo T., Muta H., Ogata K., Uno M., Yamanaka S.
Study on the Role of Second Phase Particles in Hydrogen Uptake Behavior of Zirconium Alloys
Li Q., Peng J., Wang J., Yao M., Zhou B.
Hydride Platelet Reorientation in Zircaloy Studied with Synchrotron Radiation Diffraction
Almer J., Colas K., Daymond M., Kerr M., Motta A.
Statistical Analysis of Hydride Reorientation Properties in Irradiated Zircaloy-2
Alam A., Bertsch J., Valance S.
The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding—An International Atomic Energy Agency Coordinated Research Program
Chakravartty J., Coleman C., Grigoriev V., Inozemtsev V., Kim Y., Lalgudi R., Liaqat Ali K., Makarevicius V., Markelov V., Mizrahi R., Roth M.
Neutron Radiography: A Powerful Tool for Fast, Quantitative and Non-Destructive Determination of Hydrogen Concentration and Distribution in Zirconium Alloys
Grosse M.
Detailed Analysis of the Microstructure of the Metal/Oxide Interface Region in Zircaloy-2 after Autoclave Corrosion Testing
Andersson T., Andrén H., Ciurea S., Dahlbäck M., Hallstadius L., Tejland P., Thuvander M.
Study of the Initial Stage and Anisotropic Growth of Oxide Layers Formed on Zircaloy-4
Du C., Li Q., Peng J., Xia S., Xu G., Yao M., Zhou B.
Studies Regarding Corrosion Mechanisms in Zirconium Alloys
Ambard A., Blat-Yrieix M., Chong K., Comstock R., Cottis B., English C., Fitzpatrick M., Frankel P., Grovenor C., Hallstadius L., Hudson D., Lozano-Perez S., Lyon S., Ni N., Polatidis E., Preuss M., Smith G., Smith J., Storer S., Sykes J., Wang P., Wei J.
Understanding Crack Formation at the Metal/Oxide Interface During Corrosion of Zircaloy-4 Using a Simple Mechanical Model16th International Symposium on Zirconium in the Nuclear Industry, 9th May 2010 – 13th May 2010, Chengdu, Sichuan Province, China
Ambard A., Blat-Yrieix M., Bréchet Y., Curfs C., Frankel P., Legras L., Ly A., Parry G., Preuss M.
Optimization of Zry-2 for High Burnups
Cox B., Garzarolli F., Rudling P.
Effects of Secondary Phase Particle Dissolution on the In-Reactor Performance of BWR Cladding
Abolhassani S., Dahlbäck M., Hallstadius L., Jädernäs D., Ledergerber G., Mader E., Valizadeh S., Wright J., Zhou G.
Hydrogen Solubility and Microstructural Changes in Zircaloy-4 Due to Neutron Irradiation
Banchik A., Bozzano P., Flores A., Ríos R., Versaci R., Vizcaíno P.
Advanced Zirconium Alloy for PWR Application
Baranwal R., Carrera F., Comstock R., Cook T., Garde A., Hallstadius L., Pan G.
Ultra Low Tin Quaternary Alloys PWR Performance—Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties
Barberis P., Chabretou V., Garner G., Hoffmann P., Rebeyrolle V., Trapp-Pritsching S., Vermoyal J.
Radiation Damage of E635 Alloy Under High Dose Irradiation in the VVER-1000 and BOR-60 Reactors
Kobylyansky G., Markelov V., Novoselov A., Obukhov A., Ostrovsky Z., Peregud M., Shishov V.
ZIRLO® Irradiation Creep Stress Dependence in Compression and Tension
Baranwal R., Foster J.
Experimental Investigation of Irradiation Creep and Growth of Recrystallized Zircaloy-4 Guide Tubes Pre-Irradiated in PWR
McGrath M., Yagnik S.
REFLET Experiment in OSIRIS: Relaxation under Flux as a Method for Determining Creep Behavior of Zircaloy Assembly Components
Audic K., Bernaudat C., Bouffioux P., Carassou S., Chabretou V., Cloué J., Duguay C., Levasseur B., Maurice A., Rozenblum F., Yvon P.
Impact of Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys
Bouffioux P., Bourdiliau B., Cappelaere C., Chabretou V., Miquet A., Onimus F., Pivetaud V.
Shadow Corrosion-Induced Bow of Zircaloy-2 Channels
Cantonwine P., Crawford D., Edsinger K., Lin Y., Mader E., Mahmood S.
Characterization of Oxygen Distribution in LOCA Situations
Bělovský L., Desquines J., Duriez C., Grandjean C., Guilbert S., Stern A.
Effect of Hydrides on Mechanical Properties and Failure Morphology of BWR Fuel Cladding at Very High Strain Rate
Nakatsuka M., Yagnik S.
Simulation of Outside-in Cracking in Boiling Water Reactor Fuel Cladding Tubes under Power Ramp
Higuchi T., Nakatsuka M., Sakamoto K.
RIA Failure of High Burnup Fuel Rod Irradiated in the Leibstadt Reactor: Out-of-Pile Mechanical Simulation and Comparison with Pulse Reactor Tests
Fuketa T., Grigoriev V., Hallstadius L., Jakobsson R., Ledergerber G., Nagase F., Schrire D., Sugiyama T., Valizadeh S.
Author and Subject Index
Committee: B10
Paper ID: STP1529-EB
DOI: 10.1520/STP1529-EB
ISBN-EB: 978-0-8031-8893-8
 ASTM International is a member of CrossRef.
978-0-8031-7515-0
STP1529-EB
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