PRESENTATIONS

Dynamic Recrystallization in Zirconium Alloys
J.K. Chakravartty, R. Kapoor, A. Sarkar, and S. Banerjee

Measurement and Modeling of Second Phase Precipitation Kinetics in Zirconium Alloys
J. Robson, M. Preuss, and M. Ivermark

The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding: an IAEA Coordinated Research Programme
C. Coleman, V. Grigoriev, V. Inozemtsev, V. Markelov, M. Roth, V. Markarevicius, Y. S. Kim, K. L. Ali, J.K. Chakravarrty, R. Mizrahi, and R. Lalgudi

Texture Evolution of Zircaloy-2 during Beta Quenching: Effect of Process Variables
J. Romero, J. Quinta da Fonseca, M. Preuss M. Dahlbäck,, L. Hallstadius, R. Comstock

In Situ Study of Variant Selection During the α-β-α Phase Transformation in Zr-2.5Nb
P. Mosbrucker, M.R. Daymond, and R.A. Holt

Development of Zr 2.5Nb Pressure Tubes for Advanced CANDU Reactor
G. Bickel, M. Griffiths, A. Douchant, S. Douglas, O. T. Woo, and A. Buyers

Microstructural Studies of Heat Treated Zr-2.5 Nb Alloy for Pressure Tube Applications
N. Saibaba, S. K. Jha, S. Tonpe, V. Kumar, V. Deshmukh, D. Srivastava, K.V. ManiKrishna, S. Neogy, G. K. Dey, R. V. Kulkarni, B.B. Rath, E. Ramadasan, and K. Ananthraman

Segregation in Vacuum Arc Remelted Zirconium Alloy Ingots
A. Jardy, M. Revil-Baudard, F. Leclerc, P. Guerin, and V. Rebeyrolle

Damage Build-Up in Zirconium Alloys Mechanical Processing and Impacts on Quality of the Cold Pilgering Product
A. Gaillac, P. Barberis, C. Lemaignan

Effect of Texture on the Anisotropic Thermal Creep of Pressurized Zr-2.5Nb Tubes
W. Li and R.A. Holt

Creep of a Zr-2.5Nb Tube with Orientation and Temperature
Y.S. Kim and S.S. Kim

Micromechanical Approach of Visco-Plastic Behavior of Zircaloy-4 Recrystallized at 400ºC
M. Priser, P. Pilvin, M. Rautenberg, J.M. Cloué, D. Poquillon, and X. Feaugas

Crack Growth in the Through-Thickness Direction of Hydrided Thin-Wall Zircaloy Sheet
P. A. Raynaud, D. A. Koss, A. T. Motta, K. S. Chan

High Temperature Aqueous Corrosion and Deuterium Uptake of Coupons Prepared from the Front and Back Ends of Zr-2.5Nb Pressure Tubes
H. M. Nordin, A. J. Elliot, and S. G. Bergin

Hydrogen Absorption Mechanism of Zirconium Alloys Based on the Characterization of Oxide Layer
K. Une, M. Aomi, K. Sakamoto, J. Matsunaga, Y. Etoh, I. Takagi, S. Miyamura, T. Kobayashi, and K. Ito

In-situ SEM Observation and FEM Analysis of Delayed Hydride Cracking Propagation in Zircaloy-2 Fuel Cladding Tubes
T. Kubo, H. Muta, S. Yamanak, M. Uno, and K. Ogata

The Effect of Second Phase Particles on the Hydrogen Uptake Performance of Zirconium Alloys Corroded in Super-Heated Steam
M.Y. Yao, J.H Wang, B.X. Zhou, Q. Li, and J.L. Zhang

In-Situ Study of Hydride Reorientation Kinetics Using Synchrotron Radiation
K. Colas and A. Motta, Penn State University, University Park, PA, USA; M. Daymond and M. Kerr, Queen’s University, Kingston, ON, Canada; and J. Almer, Argonne National Laboratory, Argonne, IL, USA

Analysis of Hydride Reorientation Properties in Irradiated Zircaloy-2
S. Valance, J. Bertsch, A.M. Alam

Detailed Microstructure of the Oxide-Metal Interface Region in Zircaloy-2 after Autoclave Testing
P. Tejland, H. O. Andrén, S. Ciuera, T. Andersson, M. Dahlbäck, and L. Hallstadius

Study of the Initial Stage and Anisotropic Growth of Oxide Layers Formed on Zircaloy-4
B. X. Zhou, J. C. Peng, M. Y. Yao, Q. Li, S. Xia, C. X. Du, and G. Xu

Towards a Mechanistic Understanding of Corrosion Mechanisms in Zirconium Alloys
M. Preuss, P. Frankel, E. Polatidis, J. Wei, J. Smith, C. English, F. Wang, B. Cottis, S. Lyon, S. Lozano-Perez, D. Hudson, N. Ni, C. Grosvenor, G. Smith, J. Sykes, A. Cerezo, and S. Storer, M. Fitzpatrick

Zirconium alloys microstructure effect on their corrosion kinetics: Case of Zircaloy-4
A. Ly, A. Ambard, M. Blat-Yrieix, L. Legras, Y. Bréchet, P. Frankel, M. Preuss, C. Curfs

Corrosion of M5 in PWRs: Quantification of Li, B, H and Nb in the Oxide Layers Formed Under Different Conditions
P. Bossis, M. Tupin, C. Bisor-Melloul, C. Raepsaet, H. Khodja, M. Blat, A. Ambard, A. Miquet, and D. Kaczorowski

Advanced Zirconium Alloy for PWR Application
A. Garde, R. Baranwal, G. Pan, R. J. Comstock, L. Hallstadius, T. Cook, and F. Carrera

Photoelectrochemical Investigation of Radiation Enhanced Shadow Corrosion Phenomenon
Y.- J. Kim, R. Rebak, Y-P. Lin, D. Lutz, D. Crawford, A. Kucuk and B. Cheng

Optimization of Zry-2 for High Burnups
F. Garzarolli, B. Cox, and P. Rudling

Effects of Secondary Phase Particle Dissolution on the In-Reactor Performance of BWR Cladding
S. Valizadeh, M. Dahlbäck, J. Wright, G. Zhou, L. Hallstadius, G. Ledergerber, S. Abolhassani, R. J. Comstock, D. Jädernäs, and E. Mader

Hydrogen Solubility and Microstructural Changes in Zircaloy-4 due to Neutron Irradiation
P. Vizcaíno, A. V. Flores, A. D. Banchik, R. O. Ríos, P. B. Bozzano, and R. A. Versaci

Ultra Low Tin Quaternary Alloys In-Pile Performance Impact of Tin Content on Corrosion and Mechanical Resistance
V. Chabretou, J. J. Vermoyal, P.B. Hoffmann, S. Trapp-Pritsching, G. Garner, P. Barberis, and, V. Rebeyrolle

Radiation Damage of E635 Alloy under High Dose Irradiation in the VVER-1000 and BOR-60 Reactors
G. P. Kobylyansky, A. E. Novoselov, A. V. Obukhov, Z. E. Ostrovsky, V. N. Shishov, M. M. Peregud, and V.A. Markelov

Simulation of Outside-in Cracking in BWR Fuel Cladding Tubes under Power Ramp
K. Sakamoto, M. Nakatsuka, and T. Higuchi

ZIRLOTM Irradiation Creep Stress Dependence in Compression and Tension
John Foster and Rita Baranwal

Neutron Radiography a Powerfull Tool For Fast, Quantiative and Nondestructive Determination Of The Hydrogen Concentration and Distribution In Zirconium Alloys
Mirco Grosse, Martin Steinbrück and Juri Stuckert

Impact of the Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys
B. Bourdillau, F. Onimus, C. Cappelaere, V. Pivetaud, P. Bouffioux, V. Chabretou, and A. Miquet

Effects of Pre-Irradiation on Irradiation Creep and Growth of Recrystallized Zircaloy-4
M. McGrath, H.K. Jenssen, and S. Yagnik

REFLET Experiment in OSIRIS: Relaxation under Flux for Creep Behavior of Assembly Components
S. Carassou, P. Yvon, F. Rozenblum, C. Duguay, J.M. Cloué, V. Chabretou, C. Bernaudat, B. Levasseur, A. Maurice, P. Bouffioux, and K. Audic

Shadow Corrosion-Induced Bow of Zircaloy-2 Channels
S. T. Mahmood, P. E. Cantonwine, Y-P. Lin, D. C. Crawford, V. Mader, and K. Edsinger

Characterization of Oxygen Distribution in LOCA Situations
C. Duriez, A. Stern, S. Guilbert, C. Grandjean, L. Bělovský, and J. Desquines

Effect of Hydrogen on Mechanical Properties and Failure Morphology of LWR Fuel Cladding Tubes under Rapid Deformation
M. Nakatsuka and S. Yagnik

The Iodine-induced Stress Corrosion Crack Behavior of Zr-Sn-Nb Alloy at Constant Strain Rate
X. Dai and W. Zhao

RIA Failure of High Burn-up Fuel Rod Irradiated in KKL: Out-of-Pile Mechanical Simulation and Comparison with Pulse Reactor Tests
V. Grigoriev, R. Jakobsson, D. Schrire, G. Ledergerber, T. Sugiyama, F. Nagase, T. Fuketa, L. Hallstadius, and S. Valizadeh

POSTERS

Phase Transformations in Zr-Nb-Fe-Sn System Alloys
V.N. Shishov

Secondary Hydriding Criteria under Irradiation Conditions
I.A. Evdokimov, V.V. Likhanskii, A.A. Sorokin, and V.D. Kanukova

Investigation of the Interaction between Gliding Dislocations and Irradiation Induced Loops in Zirconium Alloys - Part 1, Part 2
F. Onimus, L. Dupuy, and B. Doisneau-Cottignies

Nano-chemical Observations of Zirconium Alloy Corrosion using 3D Atom Probe
D. Hudson, N. Ni, D. W. Saxey, G. D. W Smith, and C. R. M. Grovenor

Validation of Weight Function Process-Zone Model for Flaw Evaluation against Delayed Hydride Cracking Initiation
S. X. Xu, D. A. Scarth, and D. Kawa

High Temperature Oxidation and Residual Ductility of Fuel Claddings from Zr-1Nb Alloy Having Different Contents of Impurities
V. Markelov, V.V. Novikov, A. V. Nikulina, A. G. Malgin, A. Y. Gusev, A. G. Ziganshin,V. E. Donnikov, V. I. Latunin, and Y. V. Pimenov

KROLL PRESENTATIONS

Explosion Cladding, an Enabling Technology for Zirconium in the Chemical Process Industry
J.G. Banker

The Development of Zr-2.5 Nb Pressure Tubes for CANDU Reactors
B.A. Cheadle

The Evolution of Microstructure and Deformation Stability in Zr-Nb-Fe (Sn,O) Alloys Under Neutron Irradiation
V.Shishov