Grain-by-Grain Study of the Mechanisms of Crack Propagation During Iodine Stress Corrosion Cracking of Zircaloy-4 / RE. Haddad, AO. Dorado
- Conference Author:
- Zirconium in the Nuclear Industry: Tenth International Symposium (10th : 1993 : Baltimore, MD)
- Physical Description:
- 1 online resource (17 pages) : illustrations, figures, tables
- Additional Creators:
- Dorado, AO., Haddad, RE., American Society for Testing and Materials, and ASTM International
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- Machine generated contents note: Development of Zirconium-Barrier Fuel Cladding / J. S. Armijo / L. F. Coffin / H. S. Rosenbaum -- Zirconium Alloy Performance in Light Water Reactors: A Review of UK and Scandinavian Experience / D. O. Pickman -- The Effect of Fluence and Irradiation Temperature on Delayed Hydride Cracking in Zr-2.5Nb / S. Sagat / C. E. Coleman / M. Griffiths / B. J. S. Wilkins -- A Study of the Hydrogen Uptake Mechanism in Zirconium Alloys / M. B. Elmoselhi / B. D. Warr / S. McIntyre -- Hydrogen Absorption Kinetics During Zircaloy Oxidation in Steam / D. Charquet / P. Rudling / M. Mikes-Lindback / P. Barberis -- Scanning Electron Microscope Techniques for Studying Zircaloy Corrosion and Hydriding / D. I. Schrire / J. H. Pearce -- Growth and Characterization of Oxide Films on Zirconium-Niobium Alloys / V. F. Urbanic / P. K. Chan / D. J. Khatamian / O.-T. T. Woo -- Correlation Between Irradiated and Unirradiated Fracture Toughness of Zr-2.5Nb Pressure Tubes / P. H. Davies / R. R. Hosbons / M. Griffiths / C. K. Chow -- Variability of Irradiation Growth in Zr-2.5Nb Pressure Tubes / R. G. Fleck / J. E. Elder / A. R. Causey / R. A. Holt -- Change of Mechanical Properties by Irradiation and Evaluation of the Heat-Treated Zr-2.5BNb Pressure Tube / M. H. Koike / T. Akiyama / K. Nagamatsu / I. Shibahara -- On the Anisotropy of In-Reactor Creep of Zr-2.5BNb Tubes / A. R. Causey / J. E. Elder / R. A. Holt / R. G. Fleck -- Fabrication of Zr-2.5Nb Pressure Tubes to Minimize the Harmful Effects of Trace Elements / J. R. Theaker / R. Choubey / G. D. Moan / S. A. Aldridge / L. Davis / R. A. Graham / C. E. Coleman -- Modeling of Damage in Cold Pilgering / J. L. Aubin / E. Girard / P. Montmitonnet -- Mitigation of Harmful Effects of Welds in Zirconium Alloy Components / C. E. Coleman / G. L. Doubt / R. W. L. Fong / J. H. Root / J. W. Bowden / S. Sagat / R. T. Webster -- Fabrication Process of High Nodular Corrosion-Resistant Zircaloy-2 Tubing / H. Abe / K. Matsuda / T. Hama / T. Konishi / M. Furugen -- Corrosion Behavior of Zircaloy-4 Sheets Produced Under Various Hot-Rolling and Annealing Conditions / H. Anada / K. Nomoto / Y. Shida -- Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Improving the Manufacturing and Inspection Process / J.-P. Mardon / D. Charquet / J. Senevat -- Experimental and Theoretical Studies of Parameters that Influence Corrosion of Zircaloy-4 / Ph. Billot / J.-C. C. Robin / A. Giordano / J. Peybernes / J. Thomazet / H. Amanrich -- Aqueous Chemistry of Lithium Hydroxide and Boric Acid and Corrosion of Zircaloy-4 and Zr-2.5Nb Alloys / N. Ramasubramanian / P. V. Balakrishnan -- Corrosion Behavior of Irradiated Zircaloy / B.-C. Cheng / R. M. Kruger / R. B. Adamson -- Correlation of Transmission Electron Microscopy (TEM) Microstructure Analysis and Texture with Nodular Corrosion Behavior for Zircaloy 2 / B. J. Herb / J. M. McCarthy / C. T. Wang / H. Ruhmann -- Micro-Characterization of Corrosion-Resistant Zirconium-Based Alloys / T. Isobe / Y. Matsuo / Y. Mae -- An Experimental Investigation into the Oxidation of Zircaloy-4 at Elevated Pressures in the 750 to 1000[degree]C Temperature Range / I. L. Bramwell / T. J. Haste / D. Worswick / P. D. Parsons -- Prediction of Creep Anisotropy in Zircaloy Cladding / R. A. Perkins / S.-H. Shann -- Microstructure and Properties of Corrosion-Resistant Zirconium-Tin-Iron-Chromium-Nickel Alloys / E. R. Bradley / A.-L. Nystrom -- Fatigue Behavior of Irradiated and Unirradiated Zircaloy and Zirconium / S. B. Wisner / M. B. Reynolds / R. B. Adamson -- Effect of Irradiation on the Microstructure of Zircaloy-4 / D. Gilbon / C. Simonot -- Irradiation Effect on Fatigue Behavior of Zircaloy-4 Cladding Tubes / A. Soniak / S. Lansiart / J. Royer / J.-P. Mardon / N. Waeckel -- Grain-by Grain Study of the Mechanisms of Crack Propagation During Iodine Stress Corrosion Cracking of Zircaloy-4 / R. E. Haddad / A. O. Dorado -- Microstructure of Oxide Layers Formed During Autoclave Testing of Zirconium Alloys / B. Wadman / Z. Lai / H.-O. Andren / A.-L. Nystrom / P. Rudling / H. Pettersson -- Corrosion Performance of New Zircaloy-2 Based Alloys / P. Rudling / M. Mikes-Linback / B. Lethinen / H.-O. Andren / K. Stiller -- Examinations of the Corrosion Mechanism of Zirconium Alloys / H. J. Beie / A. Mitwalsky / F. Garzarolli / H. Ruhmann / H.-J. Sell -- On the Initial Corrosion Mechanism of Zirconium Alloy: Interaction of Oxygen and Water with Zircaloy at Room Temperature and 450[degree]C Evaluated by X-Ray Absorption Spectroscopy and Photoelectron Spectroscopy / U. Dobler / A. Knop / H. Ruhmann / H.-J. Beie -- How the Tetragonal Zirconia is Stabilized in the Oxide Scale that is Formed on a Zirconium Alloy Corroded at 400[degree]C in Steam / J. Godlewski -- Oxidation of Intermetallic Precipitates in Zircaloy-4: Impact of Radiation / D. Pecheur / F. Lefebvre / A. T. Motta / C. Lemaignan / D. Charquet -- Corrosion Optimized Zircaloy for Boiling Water Reactor (BWR) Fuel Elements / F. Garzarolli / R. Schumann / E. Steinberg -- In-Reactor Corrosion Performance of ZIRLO and Zircaloy-4 / G. P. Sabol / R. J. Comstock / R. A. Weiner / P. Larouere / R. N. Stanutz -- Phenomenological Study of In-Reactor Corrosion of Zircaloy-4 in Pressurized Water Reactors / Y. S. Kim / K. S. Rheem / D. K. Min -- Corrison Behavior of Zircaloy-4 Cladding with Varying Tin Content in High-Temperature Pressurized Water Reactors / A. M. Garde / S. P. Pati / M. A. Krammen / G. P. Smith / R. K. Endter -- Effects of Pressurized Water Reactor (PWR) Coolant Chemistry on Zircaloy Corrosion Behavior / T. Karlsen / C. Vitanza.
- Summary:
- This paper describes the tests conducted to determine the conditions leading to cracking of a specified grain of metal, during the iodine stress corrosion cracking (SCC) of zirconium alloys, focusing on the crystallographic orientation of crack paths, the critical stress conditions, and the significance of the fractographic features encountered. In order to perform crystalline orientation of fracture surfaces, a specially heat-treated Zircaloy-4 having very large grains, grown up to the wall thickness, was used. Careful orientation work has proved that intracrystalline pseudo-cleavage occurs only along basal planes. The effects of anisotropy, plasticity, triaxiality, and residual stresses originated in thermal contraction have to be considered to account for the influence of the stress state. A grain-by-grain calculation led to the conclusion that transgranular cracking always takes place on those bearing the maximum resolved tensile stress perpendicular to basal planes. Propagation along twin boundaries has been identified among the different fracture modes encountered.
- Dates of Publication and/or Sequential Designation:
- Volume 1994, Issue 1245 (January 1994)
- Subject(s):
- Other Subject(s):
- ISBN:
- 0803120117
9780803120112
9780803152861 (e-ISBN) - Digital File Characteristics:
- text file PDF
- Bibliography Note:
- Includes bibliographical references 17.
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- Electronic reproduction. W. Conshohocken, Pa. : ASTM International, 1994. Mode of access: World Wide Web. System requirements: Web browser. Access may be restricted to users at subscribing institutions.
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