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Simulating the Behavior of Zirconium-Alloy Components in Nuclear Reactors / CE Coleman -- Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys / C Lemaignan -- Role of the Second-Phase Particles in Zirconium Binary Alloys -- P Barberis, E Ahlberg, N Simic, D Charquet, C Lemaignan, G Wikmark, M Dahlbäck, M Limbäck, P / Tägtström, B Lehtinen -- Synchrotron Radiation Study of Second-Phase Particles and Alloying Elements in Zirconium Alloys / AT Motta, KT Erwin, O Delaire, RC Birtcher, Y Chu, J Maser, DC Mancini, B Lai -- The Behavior of Intermetallic Precipitates in Highly Irradiated BWR LTP Cladding / W Goll, L Ray -- Effects of Hydrogen Pickup and Second-Phase Particle Dissolution on the In-Reactor Corrosion Performance of BWR Claddings / P Tägtstrom, M Limbäck, M Dahlbäck, T Andersson, H Pettersson -- Alternative Zr Alloys with Irradiation Resistant Precipitates for High Burnup BWR Application / F Garzarolli, H Ruhmann, L Van Swam -- Mössbauer Investigations of the Chemical States of Tin and Iron Atoms in Zirconium Alloy Oxide Film / D Pêcheur, VP Filippov, AB Bateev, JJ Ivanov -- Chemical State Analysis of Sn and Fe in ZrO by Mössbauer Spectroscopy / H Anada, K Takeda, S Nasu, Y Kobayashi, T Nakamichi -- The Role of Lithium and Boron on the Corrosion of Zircaloy-4 Under Demanding PWR-Type Conditions / P Billot, S Yagnik, N Ramasubramanian, J Peybernes, D Pêcheur -- Study of the Mechanisms Controlling the Oxide Growth Under Irradiation: Characterization of Irradiated Zircaloy-4 and Zr-1Nb-O Oxide Scales / P Bossis, J Thomazet, F Lefebvre -- Hydrogen Evolution and Pickup During the Corrosion of Zirconium Alloys: A Critical Evaluation of the Solid State and Porous Oxide Electrochemistry / N Ramasubramanian, P Billot, S Yagnik -- The Influence of Material Variables on Corrosion and Deuterium Uptake of Zr-2.5Nb Alloy During Irradiation / GM McDougall, VF Urbanic -- The Cause for Enhanced Corrosion of Zirconium Alloys by Hydrides / YS Kim, HK Woo, KS Im, SI Kwun -- The Effect of Minor Alloying Elements on Oxidation and Hydrogen Pickup in Zr-2.5Nb / RA Ploc -- Role of Microchemistry and Microstructure on Variability in Corrosion and Deuterium Uptake of Zr-2.5Nb Pressure Tube Material / BD Warr, V Perovic, YP Lin, AC Wallace -- Temperature and Hydrogen Concentration Limits for Delayed Hydride Cracking in Irradiated Zircaloy / JS Schofield, EC Darby, CF Gee -- Experimental Study and Preliminary Thermodynamic Calculations of the Pseudo-Ternary Zr-Nb-Fe-(O,Sn) System / C Toffolon, J-C Brachet, C Servant, L Legras, D Charquet, P Barberis, JP Mardon -- Activated Slip Systems and Localized Straining of Irradiated Zr Alloys in Circumferential Loadings / C Regnard, B Verhaeghe, F Lefebvre-Joud, C Lemaignan -- Effects of Neutron Irradiation on the Microstructure of Alpha-Annealed Zircaloy-4 / R Bajaj, BF Kammenzind, DM Farkas -- Plastic Deformation and Fracture During the Zr1%Nb Tube Production / SY Zavodtchikov, LB Zuev, VI Belov, AF Lositskiy, YP Shevnin -- Development of Crystallographic Texture in CANDU Calandria Tubes / JR Theaker, CE Coleman -- Impact of Hydrogen on Dimensional Stability of ZIRLO Fuel Assemblies / SJ King, RL Kesterson, KH Yueh, RJ Comstock, WM Herwig, SD Ferguson -- In-PWR Irradiation Performance of Dilute Tin-Zirconium Advanced Alloys / AM Garde, GP Smith, RC Pirek -- Predicting the In-Reactor Mechanical Behavior of Zr-2.5Nb Pressure Tubes from Postirradiation Microstructural Examination Data / M Griffiths, PH Davies, WG Davies, S Sagat -- The Influence of In-Situ Clad Straining on the Corrosion of Zircaloy in a PWR Water Environment / BF Kammenzind, KL Eklund, R Bajaj -- Characteristics of Hydride Precipitation and Reorientation in Spent-Fuel Cladding / HM Chung, RS Daum, JM Hiller, MC Billone -- Test Reactor Studies of the Shadow Corrosion Phenomenon / B Andersson, M Limbäck, G Wikmark, E Hauso, T Johnsen, RG Ballinger, AC Nystrand -- An In-Reactor Simulation Test to Evaluate Root Cause of Secondary Degradation of Defective BWR Fuel Rod / B Cheng, BC Oberländer, W Wiesenack, S Yagnik, J Turnbull -- The Effect of Short-Term Dry-Out Transients on the Cladding Properties of Fresh and Pre-Irradiated Fuel Rods / MA McGrath, BC Oberländer, S Thorshaug, H Ruhmann, T Anegawa, T Hara -- Effects of Alpha-Beta Transformation on High Temperature (LOCA) Creep behavior of Zr-Alloys / HJ Sell, E Ortlieb -- Influence of Hydrogen Content on the a/ß Phase Transformation Temperatures and on the Thermal-Mechanical Behavior of Zy-4, M4 (ZrSnFeV), and M5™ (ZrNbO) Alloys During the First Phase of LOCA Transient / J-C Brachet, L Portier, T Forgeron, J Hivroz, D Hamon, T Guilbert, T Bredel, P Yvon, J-P Mardon, P Jacques -- On the Embrittlement of Zircaloy-4 Under RIA-Relevant Conditions / RS Daum, S Majumdar, DW Bates, AT Motta, DA Koss, MC Billone -- Impact of Irradiation Defects Annealing on Long-Term Thermal Creep of Irradiated ircaloy-4 Cladding Tube / C Cappelaere, R Limon, D Gilbon, T Bredel, O Rabouille, P Bouffioux, JP Mardon -- Influence of Composition and Condition on In-PWR Behavior of Zr-Sn-Nb-FeCrV Alloys / A Seibold, F Garzarolli -- Influence of Zirconium Alloy Chemical Composition on Microstructure Formation and Irradiation Induced Growth / VN Shishov, MM Peregud, AV Nikulina, PV Shebaldov, AV Tselischev, AE Novoselov, GP Kobylyansky, ZE Ostrovsky, VK Shamardin -- Quantitative Assessment of Irradiation Effect on Creep and Corrosion Properties of Zr-Base Alloys / T Kido, Y Senda, Y Tukuta, H Hayashi, K Murai -- Variability of In-Reactor Diametral Deformation for Zr-2.5Nb Pressure Tubing / M Griffiths, WG Davies, AR Causey, GD Moan, RA Holt, SA Aldridge -- About the Mechanisms Governing the Hydrogen Effect on Viscoplasticity of Unirradiated Fully Annealed Zircaloy-4 Sheet / N Rupa, M Clavel, P Bouffioux, C Domain, A Legris -- Irradiation Creep Behavior of Zr-Base Alloys / A Soniak, N L'Hullier, J-P Mardon, V Rebeyrolle, P Bouffioux, C Bernaudat -- The Effect of Small Concentrations of Sulfur on the Plasticity of Zirconium Alloys at Intermediate Temperatures / F Ferrer, A Barbu, T Bretheau, J Crépin, F Willaime, D Charquet -- Author Index -- Subject Index.
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Zirconium in the Nuclear Industry: 4th Conference
