Zirconium in the Nuclear Industry: Thirteenth International Symposium

• Pubblicazione: [Place of publication not identified], : American Society for Testing & Materials, 2002
• Descrizione fisica: 1 online resource (881 pages) : illustrations
• Disciplina: 621.48335
• Soggetto topico: Nuclear fuel claddings; Zirconium alloys
• Persona (resp. second.): MoanGerry D; RudlingPeter
• Note generali: Bibliographic Level Mode of Issuance: Monograph
• Nota di contenuto: 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.
• Sommario/riassunto: The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
• Altri titoli varianti: Zirconium in the Nuclear Industry
• Titolo autorizzato: Zirconium in the Nuclear Industry: Thirteenth International Symposium
• ISBN: 0-8031-5468-2
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910164280603321
• Lo trovi qui: Univ. Federico II
• Serie: ASTM special technical publication ; ; 1423.