About the Book
This CD encapsulates an international forum on the exchange of research results and reactor operating experiences associated with materials degradation in water-cooled nuclear power reactor systems. The 131 papers included cover degradation phenomena particular to the various reactor systems, BWRs, PWR primary and PWR secondary, as well as narrow topic areas, such as zircalloy and low alloy steels, and cross-cutting topics, such as nickel-base welds, irradiation effects, and irradiation assisted stress corrosion cracking. The subject of environmental effects in supercritical water is also covered. What makes this compilation of even greater value is the question-and-answer section following each paper, which represents the dialogue that occurred between the speaker and the audience of scientists and engineers from 15 countries. Professionals representing utilities, reactor vendors, regulators, national laboratories and universities will find this publication of great value.
Table of Contents:
Foreword. Session Chairs. Financial Sponsors. BWR SCC & Modeling. Advances in Electrochemical Corrosion Potential Monitoring in Boiling Water Reactors ( S. Hettiarachchi ). Effects of Hydrogen Peroxide and Oxygen on Corrosion of Stainless Steel in High Temperature Water ( S. Uchida, T. Satoh, Y. Morishima, T. Hirose, T. Miyazawa, N. Kakinuma, Y. Satoh, N. Usui, and Y. Wada ). Effect of the Plastic Strain Level Quantified by EBSP Method on the Stress Corrosion Cracking of L-Grade Stainless Steels ( Y. Katayama, M. Tsubota, and Y. Saito ). Correlation Between Deformation-Induced Microstructures and TGSCC Susceptibility in a Low Carbon Austenitic Stainless Steel ( A. Kimura, T. Noda, H. Ohkubo, Y. Kamada, and S. Takahashi ). The Initiation of Environmentally Assisted Cracking in BWR High Temperature Water ( S. Wang, Y. Takeda, K. Sakaguchi, and T. Shoji ). Stress Corrosion Cracking of Type 316 and 316L Stainless Steels in High Temperature Water ( N. Ishiyama, M. Mayuzumi, Y. Mizutani, and J.-i. Tani ). Crack Growth Behaviors of Low Carbon 316 Stainless Steels in 288-C Pure Water ( M. Itow, M. Itatani, M. Kikuchi, and N. Tanaka ). Influence of Heat Treatment, Aging and Neutron Irradiation on the Fracture Toughness and Crack Growth Rate in BWR Environments of Alloy X-750 ( A. Jenssen, P. Efsing, and J. Sundberg ). Effects of Si on SCC of Irradiated and Unirradiated Stainless Steels and Nickel Alloys ( P.L. Andresen, and M.M. Morra ). Stress Corrosion Crack Growth Behavior of Cold Worked Austenitic Stainless Steel in High Temperature Water ( M. Tsubota, Y. Katayama, and Y. Saito ). Finite Element Calculation of Crack Propagation in Type 304 Stainless Steel in Diluted Sulphuric Acid Solution Under Stress Corrosion Conditions ( S. Gavrilov, M. Vankeerberghen, and J. Deconinck ). The Electrochemistry of Boiling Water Reactors ( H.S. Kim, M. Urquidi-Macdonald, and D. Macdonald ). Modeling and Experimental Studies of Intergranular Corrosion in Austenitic Stainless Steels Used in Light Water Reactor Systems ( R.G. Faulkner, Y. Yin, J. Cintas, and J.M. Montes ). Evaluation of the Fracture Research Institute Theoretical Stress Corrosion Cracking Model ( E.D. Eason, R. Pathania, and T. Shoji ). Crack Growth. The Effect of Hold Time on the Crack Growth Rate of Sensitized Stainless Steel in High Temperature Water ( A. Jenssen, C. Jansson, and J. Sundberg ). Effects of Positive and Negative dK/da on SCC Growth Rates ( P.L. Andresen, and M.M. Morra ). Evaluation of Stress Corrosion Crack Growth Rate Based on Inspection Data on Alloy 600 Tubing ( Y. Garud, B. Woodman, and G. Boyers ). High-Resolution Characterizations of Stress-Corrosion Cracks in Austenitic Stainless Steel from Crack Growth Tests in BWR-Simulated Environments ( S.M. Bruemmer, and L.E. Thomas ). Zircaloy. Characterization of Oxides Formed on Model Zirconium Alloys in 360-C Water Using Micro-Beam Synchrotron Radiation ( A. Yilmazbayhan, M. Gomes da Silva, A. Motta, H.-G. Kim, Y.H. Jeong, J.-Y. Park, R. Comstock, B. Lai, and Z. Cai ). Effect of Pre-Deposited Magnetite on Deposition of Nickel Oxides on Zr Surface in 573K Pressurized Water ( J.-W. Yeon, Y. Jung, Y.-K. Choi, and W.-H. Kim ). Effect of Zinc Injection on Crevice Corrosion Resistance of Pre-Filmed Zircaloy-2 Tube Under Heat Transfer Condition ( H. Kawamura, H. Kanbe, R. Morita, and F. Inada ). Transient Oxide Film Growth on Zirconium in High Temperature Aqueous Solutions ( Y. Chen, M. Urquidi-Macdonald, and D.D. Macdonald ). Irradiation Assisted Stress Corrosion Cracking. The Effect of Oversize Solute Additions on the Irradiation-Assisted Stress Corrosion Cracking Resistance of Austenitic Stainless Steels ( M.J. Hackett, and G.S. Was ). Effect of Metallurgical Condition on Irradiation-Assisted Stress Corrosion Cracking of Commercial Stainless Steels ( J.T. Busby, and G.S. Was ). Irradiation-Assisted Stress Corrosion Cracking of Heat-Affected Zones of Austenitic Stainless Steel Welds ( R. Stoenescu, M.L. Castano, S. van Dyck, A. Roth B. van der Schaaf, C. Ohms, and D. Gavillet ). Irradiation Effects in a Highly Irradiated Cold Worked Stainless Steel Removed from a Commercial PWR ( J. Conermann, R. Shogan, K. Fujimoto, T. Yonezawa, and Y. Yamaguchi ). Crack Growth Behavior of Irradiated Austenitic Stainless Steel Weld Heat Affected Zone Material in High-Purity Water at 289-C ( O.K. Chopra, B. Alexandreanu, E.E. Gruber, and W.J. Shack ). Effect of the Accelerated Irradiation and Hydrogen/Helium Gas on IASCC Characteristics for Highly Irradiated Austenitic Stainless Steels ( K. Fujimoto, T. Yonezawa, E. Wachi, Y. Yamaguchi, M. Nakano, R.P. Shogan, J.P. Massoud, and T.R. Mager ). Plastic Deformation Behavior of Type 316LN Stainless Steel in Non-Irradiated, Thermallysensitized Condition or in Irradiated Condition During SSRT ( Y. Miwa, T. Tsukada, and S. Jitsukawa ). Development of Test Techniques for In-Pile SCC Initiation and Growth Tests and the Current Status of In-Pile Testing at JMTR ( H. Ugachi, Y. Kaji, J. Nakano, Y. Matsui, K. Kawamata, T. Tsukada, N. Nagata, K. Dozaki, and H. Takiguchi ). Fractographic Observations on a Highly Irradiated AISI 304 Steel after Constant Load Tests in Simulated PWR Water and Argon and after Supplementary Tensile and Impact Tests ( A. Toivonen, U. Ehrnsten, W. Karlsen, P. Aaltonen, J-P. Massoud, and J-M. Boursier ). In-Core Crack Growth Rate Studies on Irradiated Austenitic Stainless Steels in BWR and PWR Conditions in the Halden Reactor ( T.M. Karlsen, P. Bennett, and N.W. Hogberg ). Irradiation Assisted Stress Corrosion Cracking Susceptibility of Core Component Materials ( K. Chatani, Y. Kitsunai, M. Kodama, S. Suzuki, Y. Tanaka, S. Ooki, S. Tanaka, and T. Nakamura ). Influence of the Neutron Spectrum on the Tensile Properties of Irradiated Austenitic Stainless Steels, in Air and in PWR Environment ( J-P. Massoud, M. Zamboch, P. Brabec, V.K. Shamardin, V.I. Prokhorov, and Ph. Dubuisson ). Study on SCC Growth Behavior of BWR Core Shroud ( S. Ooki, Y. Tanaka, K. Takamori, S. Suzuki, S. Tanaka, Y. Saito, T. Nakamura, T. Kato, K. Chatani, and M. Kodama ). Irradiation Effects. Influence of Localized Deformation on Irradiation-Assisted Stress Corrosion Cracking of Proton-Irradiated Austenitic Alloys ( Z. Jiao, J.T. Busby, R. Obata, and G.S. Was ). Deformation Structure in 316 Stainless Steel Irradiated in a PWR ( K. Fukuya, K. Fujii, and Y. Kitsunai ). Irradiation-Induced Microstructure, Swelling and Post-Irradiation Deformation of Stainless Steel 18Cr-10Ni-Ti Irradiated with Chromium Ions to 1-100 Dpa at 300-635-C ( O.V. Borodin, V.V. Bryk, A.S. Kalchenko, A.A. Parkhomenko, V.N. Voyevodin, and F.A. Garner ). Microstructural Study and In Situ Investigation of Strain Localization in Ions Irradiated Austenitic Stainless Steels ( C. Pokor, J-P. Massoud, P. Pareige, J. Garnier, D. Loisnard, P. Dubuisson, B. Doisneau, and Y. Brechet ). Enhancement of Deuterium Retention in Helium or C+3 Ion Implanted 18Cr10NiTi Stainess Steel ( G.D. Tolstolutskaya, V.V. Ruzhytskiy, I.E. Kopanets, S.A. Karpov, V.V. Bryk, V.N. Voyevodin, and F.A. Garner ). Microstructural Evolution in Neutron-Irradiated Stainless Steels: Comparison of LWR and Fast-Reactor Irradiations ( D. Edwards, E. Simonen, S. Bruemmer, and P. Efsing ). Dose Rate Effects on Microchemistry and Microstructure Relevant to LWR Components ( E.P. Simonen, D.J. Edwards, and S.M. Bruemmer ). Void Swelling of Austenitic Steels Irradiated with Neutrons at Low Temperatures and Very Low Dpa Rates ( F.A. Garner, S.I. Porollo, Yu.V. Konobeev, and O.P. Maksimkin ). Response of PWR Baffle-Former Bolt Loading to Swelling, Irradiation Creep and Bolt Replacement as Revealed Using Finite Element Modeling ( E.P. Simonen, F.A. Garner, N.A. Klymyshyn, and M.B. Toloczko ). LAS & RPV Steels. Boric Acid Corrosion of Light Water Reactor Pressure Vessel Materials ( J.-H. Park, O.K. Chopra, K. Natesan, W.J. Shack, and W.H. Cullen, Jr. ). The Effect of Transients on the Crack Growth Behavior of Low Alloy Steels for Pressure Boundary Components Under Light Water Reactor Operating Conditions ( A. Roth, B. Devrient, D. Gomez-Briceno, J. Lapena, M. Ernestova, M. Zamboch, U. Ehrnsten, J. Fohl, T. Weissenberg, H.-P. Seifert, and S. Ritter ). Mitigation Effect of Hydrogen Water Chemistry on Stress Corrosion and Low-Frequency Corrosion Fatigue Crack Growth in Low-Alloy Steels ( H.-P. Seifert, and S. Ritter ). Nickel-Based Weld Alloys. Examination of Stress Corrosion Cracks in Alloy 182 Weld Metal after Exposure to PWR Primary Water ( P. Scott, M. Foucault, B. Brugier, J. Hickling, and A. McIlree ). Development of Crack Growth Rate Disposition Curves for Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182, and 132 Weldments ( G.A. White, N.S. Nordmann, J. Hickling, and C.D. Harrington ). Stress Intensity and Temperature Dependence for Crack Growth Rate in Weld Metal Alloy 182 in Primary PWR Environment ( K. Norring, M. Konig, and J. Lagerstrom ). The Effect of Cold Work and Dissolved Hydrogen in the Stress Corrosion Cracking of Alloy 82 and Alloy 182 Weld Metal ( D.J. Paraventi, and W.C. Moshier ). Influence of a Cyclic Loading on the Initiation and Propagation of PWSCC in Weld Metal 182 ( F. Vaillant, J.-M. Boursier, T. Couvant, C. Amzallag, and J. Champredonde ). Microstructural and Microchemical Characterization of Primary-Side Cracks in an Alloy 600 Nozzle Head Penetration and its Alloy 182 J-Weld from the Davis-Besse Reactor Vessel ( L. Thomas, B.R. Johnson, J.S. Vetrano, and S.M. Bruemmer ). The Effect of Grain Orientation on the Cracking Behavior of Alloy 182 in PWR Environment ( B. Alexandreanu, O.K. Chopra, and W.J. Shack ). SCC Behavior in the Transitiion Region of an Alloy 182-SA 508 Cl.2 Dissimilar Weld Joint Under Simulated BWR-NWC Conditions ( Q. Peng, T. Shoji, S. Ritter, and H.-P. Seifert ). Load Path Effects on the Fracture Toughness of Alloy 82H and 52 Welds in Low Temperature Water ( C.M. Brown, and W.J. Mills ). Reduction of Toughness Results for Weld Metal 182 in a PWR Primary Water Environment with Varying Dissolved Hydrogen, Lithium Hydroxide and Boric Acid Concentrations ( B.A. Young, A. McIlree, and P.J. King ). Low Temperature Crack Propagation Evaluation in Pressurized Water Reactor Service ( A. Demma, A. McIlree, and M. Herrera ). Establishment of Experimental Conditions for the SCC Growth Rate Test of Alloy 600 and Ni Base Weld Metal in High Temperature Oxygenated Water ( M. Ozawa, Y. Yamamoto, K. Nakata, M. Itow, N. Tanaka, M. Yamamoto, and J. Kuniyai). Evaluation of SCC Crack Growth Rate in Alloy 600 and Its Weld Metals in Simulated BWR Environments ( M. Ozawa, Y. Yamamoto, K. Nakata, M. Itow, N. Tanaka, M. Kikuchi, M. Koshiishi, and J. Kuniya ). Evaluation of Mechanical and Environmental Parameters Affecting Primary Water Stress Corrosion Cracking of Nickel-Based Alloys ( J. Kwon, Y.-S. Yi, and J.-S. Kim ). Fracture Surface Morphology of Stress Corrosion Cracks in Nickel-Base Welds ( W.J. Mills ). Noble Metal & SCC Mitigation. BWR SCC Mitigation Experiences with Hydrogen Water Chemistry ( S. Hettiarachchi ). Effects of Bulk Water Chemistry on ECP Distribution Inside a Crevice ( Y. Wada, K. Ishida, M. Tachibana, and M. Aizawa ). The Impact of Oxygen and Hydrogen Recombination Efficiency on the Effectiveness of NMCA in Reducing the Corrosion Potential in Boiling Water Reactors ( T.-K. Yeh ). Online NobleChem Mitigation of SCC ( P.L. Andresen, Y.J. Kim, T.P. Diaz, and S. Hettiarachchi ). Corrosion Mitigation of BWR Structural Materials by the Photoelectric Method with TiO2 - Laboratory Experiments of TiO2 Effect on ECP Behavior and Materials Integrity ( M. Okamura, T. Osato, N. Ichikawa, T. Yotsuyanagi, Y. Tsuchiya, K. Takamori, S. Suzuki, and J. Suzuki ). Electrochemical Behavior of Oxygen and Hydrogen on ZrO2 Treated Type 304 Stainless Steels in High Temperature Pure Water ( T.-K. Yeh, C.-H. Tsai, and C.-T. Liu ). Corrosion Mitigation of BWR Structural Materials by the Photoelectric Method with TiO2- A SCC Mitigation Technique and Its Feasibility Evaluation ( K. Takamori, S. Suzuki, J. Suzuki, Y. Ishii, J. Takagi, N. Ichikawa, and Y. Fukaya ). Operational Experience. Flow Accelerated Corrosion and Cracking of Carbon Steel Piping in Primary Water- Operating Experience at the Point Lepreau Generating Station ( J.P. Slade, and T.S. Gendron ). Risk-Reduction Strategies Used to Manage Cracking of Carbon Steel Primary Coolant Piping at the Point Lepreau Generating Station ( J.P. Slade, and T.S. Gendron ). Recent In-Service Experience with Degradation of Low Alloy Steel Components Due to Localized Corrosion and Environmentally Assisted Cracking in German PWR Plants ( A. Roth, E. Nowak, M. Widera, U. Ilg, U. Wesseling and R. Zimmer ). German Experience with Intergranular Cracking in Austenitic Piping in BWRs and Assessment of Parameters Affecting the In-Service IGSCC Behavior Using an Artificial Neural Network ( R. Kilian, H. Hoffmann, U. Ilg, K. Kuster, E. Nowak, U. Wesseling, and M. Widera ). Root Cause Failure Analysis of Defected J-Groove Welds in Steam Generator Drainage Nozzles ( P. Efsing, B. Forssgren, and R. Kilian ). Laboratory Investigation of the Stainless Steel Cladding on the Davis-Besse Reactor Vessel Head ( H. Xu, S. Fyfitch, and J.W. Hyres ). Laboratory Investigation of PWSCC of CRDM Nozzle 3 and Its J-Groove Weld on the Davis-Besse Reactor Vessel Head ( H. Xu, S. Fyfitch, and J.W. Hyres ). Laboratory Investigation of the Alloy 600 Bottom Mounted Instrumentation Nozzle Samples and Weld Boat Sample from South Texas Project Unit 1 ( H. Xu, S. Fyfitch, J.W. Hyres, F. Cattant, and A. McIlree ). Boric Acid Corrosion Laboratory Investigation of the Davis-Besse Reactor Pressure Vessel Head ( H. Xu, S. Fyfitch, and J.W. Hyres ). Measurements of Carbon Steel ECP and Critical Deuterium Concentration Under CANDU Conditions in the Halden Reactor ( P.J. Bennett, M.A. McGrath, K. Bagli, and M. Dymarski ). PWR Primary. The Role of Surface Films in the Stress Corrosion Cracking of Alloy 600 in PWR Primary Water ( T.S. Mintz, and T.M. Devine ). Oxidation of Ni Base Alloys in PWR Water: Oxide Layers and Associated Damage to the Base Metal ( P. Combrade, P.M. Scott, M. Foucault, E. Andrieu, and P. Marcus ). Alloy Oxidation Studies Related to PWSCC ( F. Scenini, R.C. Newman, R.A. Cottis, and R.J. Jacko ). Effect of the Chromium Content and Strain on the Corrosion of Nickel Based Alloys in Primary Water of Pressurized Water Reactors ( F. Delabrouille, L. Legras, F. Vaillant, P. Scott, B. Viguier, and E. Andrieu ). The Mechanism and Modeling of Intergranular Stress Corrosion Cracking of Nickel-Chromium-Iron Alloys Exposed to High Purity Water ( G.A. Young, W.W. Wilkening, D.S. Morton, E. Richey, and N. Lewis ). Crack Initiation in Alloy 600 SG Tubing in Elevated pH PWR Primary Water ( R.J. Jacko, and R.E. Gold ). Initiation of SCC in Alloy 600 Wrought Materials: A Laboratory and Statistical valuation ( J. Daret ). SCC Initiation Testing of Nickel-Based Alloys Using In-Situ Monitored Uniaxial Tensile Specimens ( E. Richey, D.S. Morton, and M.K. Schurman ). Cracking of Alloy 600 Nozzles and Welds in PWRs: Review of Cracking Events and Repair Service Experience ( W. Bamford, and J. Hall ). Verification of an Intraspecimen Method Using a Constant Stress Test of Sensitized Alloy 600 ( S.K. Lee, H.S. Choi, C.B. Bahn, J.H. Kim, and I.S. Hwang ). In Search of the True Temperature and Stress Intensity Factor Dependencies for PWSCC ( D.S. Morton, S.A. Attanasio, E. Richey, and G.A. Young ). Effects of PWR Primary Water Chemistry and Deaerated Water on SCC ( P.L. Andresen, P.W. Emigh, M.M. Morra, and J. Hickling ). Crack Growth Rates in Primary Side Materials in Elevated pH PWR Water ( R.J. Jacko, and R.E. Gold ). Evaluation of Crack Growth Rate for Alloy 600 Vessel Penetrations in a Primary Water Environment ( Y. Yamamoto, M. Ozawa, K. Nakata, K. Yoshimoto, M. Toyoda, and J. Okuda ). SCC Growth Behavior of Austenitic Stainless Steels in PWR Primary Water Conditions ( C. Guerre, O. Raquet, E. Herms, M. Le Calvar, and G. Turluer ). Environmentally Assisted Crack Growth of Cold-Worked Type 304 Stainless Steel in PWR Environments ( D. Tice, N. Platts, K. Rigby, J. Stairmand, and H. Fairbrother ). SCC of Cold-Worked Austenitic Stainless Steels in PWR Conditions ( O. Raquet, E. Herms, F. Vaillant, T. Couvant, and J.-M. Boursier ). Influence of Carbide Precipitation and Rolling Direction on IGSCC Growth Behaviors of Austenitic Stainless Steels in Hydrogenated High Temperature Water ( K. Arioka, T. Yamada, T. Terachi, and G. Chiba ). Effect of Strain-Hardening on Stress Corrosion Cracking of AISI 304L Stainless Steel in PWR Primary Environment at 360-C ( T. Couvant, L. Legras, F. Vaillant, J.M. Boursier, and Y. Rouillon ). 107 Cycle Fatigue Limit of Type 304L SS in Air and PWR Water, at 150-C and 300-C ( H.D. Solomon, C. Amzallag, A.J. Vallee, and R.E. DeLair ). Statistical Analysis of the LCF Behavior of Type 304L SS Tested at 150-C and 300-C in Air and PWR Water ( H.D. Solomon, and C. Amzallag ). Comparison of the Fatigue Life of Type 304L SS as Measured in Load and Strain Controlled Tests ( H.D. Solomon, C. Amzallag, R.E. DeLair, and A.J. Vallee ). PWR Secondary. Laboratory Examination of Pulled Mill Annealed Alloy 600 Steam Generator Tube with Free Span Axial ODSCC ( A.R. Vaia, P.J. Prabhu, and J.M. Stevens ). Quantitative Morphological Characterization of Deposits Formed in the Secondary System of the Comanche Peak Steam Electric Station Using Scanning Electron Microscopy (SEM) ( S. Nasrazadani, H. Namduri, J. Stevens, and R. Theimer ). Impurity Source Terms and Behavior in Nuclear Once-Through Steam Generators [( R. Thompson ). Observations and Insights into Pb-Assisted Stress Corrosion Cracking of Alloy 600 Steam Generator Tubes ( L.E. Thomas, and S.M. Bruemmer ). Modeling Concentrated Solution Transport and Accumulation in Steam Generator Tube Support Plate Crevices ( A. Baum, and K. Evans ). Clues and Issues in the SCC of High Nickel Alloys Associated with Dissolved Lead ( R.W. Staehle ). Effect of Lead Contamination on Steam Generator Tube Degradation ( Y.C. Lu ). The Effect of Lead Ions on the Dissolution and Passivation of Nickel Base Alloys ( H. Radhakrishnan, R. Newman, and A. Carcea ). Effects of Pb on SCC of Alloy 600 and Alloy 690 in Prototypical Steam Generator Chemistries ( J. Lumsden, A. McIlree, R. Eaker, R. Thompson, and S. Slosnerick ). Evaluation of Crack Growth Rate for Alloy 600TT SG Tubing in Primary and Faulted Secondary Water Environments ( Y. Yamamoto, M. Ozawa, K. Nakata, T. Tsuruta, M. Sato, and T. Okabe ). Stress Corrosion Cracking of Nickel Alloys in "Complex" (Liquid and Vapor) Environments ( O. de Bouvier, E.-M. Pavageau, F. Vaillant, L. Legras, and F. Delabrouille ). Effect of Water Chemistry on Corrosion Resistance of Alloy 600 SG Tubes Under Acidic Conditions ( S. Fukuchi, K. Koba, H. Anada, and M. Kanzaki ). SCC Behavior of Model Alloy 600 Containing Minor Element Cerium in a Caustic Solution ( J.S. Kim, Y.-S. Yi, O.-C. Kwon, Y. Lim, and M. Jung ). A New Technique for Intergranular Crack Formation in Alloy 600 Steam Generator Tubing ( T.H. Lee, I.S. Hwang, H.S. Chung, and J.Y. Park ). Erosion-Corrosion of Alloy UNS N04400 ( G. Ogundele, A. Lloyd, S. Pagan, and F. Camacho ). Assessment of Amine Specific Effects on the Flow Accelerated Corrosion Rate of Carbon and Low Alloy Steels ( J.M. Jevec, P.J. King, C.A. Pearce, K. Fruzzetti, and K. Sedman ). Oxidation Behavior of Austenitic Materials Exposed to Secondary Side Water at 282-C ( J. Sarver, and P. King ). Characterization of Austenitic Materials Exposed to Secondary Side Water at 282-C ( S. Ramamurthy, R. Davidson, S. McIntyre, J. Sarver, and P. King ). SuperCritical Water-Cooled Reactors. Challenges and Recent Progress in Corrosion and Stress Corosion Cracking of Alloys for Supercritical Water Reactor Core Components ( G.S. Was, and S. Teysseyre ). Effect of Proton Irradiation and Grain Boundary Engineering on Stress Corrosion Cracking of Ferritic-Martensitic Alloys in Supercritical Water ( G. Gupta, and G.S. Was ). Corrosion of Zirconium-Based Fuel Cladding Alloys in Supercritical Water ( Y.H. Jeong, J.Y. Park, H.G. Kim, J.T. Busby, E. Gartner, M. Atzmon, G.S. Was, R.J. Comstock, Y.S. Chu, M. Gomes da Silva, A. Yilmazbayhan, and A.T. Motta ). Corrosion-Resistant Coatings for Use in a Supercritical Water Candu(R) Reactor ( D.A. Guzonas, J.S. Wills, G.A. McRae, S. Sullivan, K. Chu, K. Heaslip, and M. Stone ). Corrosion and Stress Corrosion Cracking of Ferritic-Martensitic Alloys in Supercritical Water ( P. Ampornrat, C.B. Bahn, and G.S. Was ). Corrosion of Candidate Materials for Supercritical Water-Cooled Reactors ( T.R. Allen, Y. Chen, L. Tan, X. Ren, K. Sridharan, and S. Ukai ). General Corrosion Properties of Titanium Based Alloys for the Fuel Claddings in the Supercritical Water-Cooled Reactor ( J. Kaneda, S. Kasahara, J. Kuniya, K. Moriya, F. Kano, N. Saito, A. Shioiri, T. Shibayama, and H. Takahashi ). Waste Materials and Mechanical Properties. Dynamic Strain Aging of Ni-Base Alloys Inconel 600 and 690 ( H. Hanninen, M. Ivanchenko, Y. Yagodzinskyy, V. Nevdacha, U. Ehrnsten, and P. Aaltonen ). Stifling of Crevice Corrosion in Alloy 22 ( K.G. Mon, G.M. Gordon, and R.B. Rebak ). Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository ( K.G. Mon, and F. Hua ). SCC Initiation and Growth Rate Studies on Titanium Grade 7 and Base Metal, Welded and Aged Alloy 22 in Concentrated Groundwater ( P.L. Andresen, G.M. Catlin, P.W. Emigh, and G.M. Gordon ). Dynamic Strain Ageing and EAC of Deformed Nitrogen-Alloyed AISI 316 Stainless Steels ( U. Ehrnsten, M. Ivanchenko, V. Nevdacha, Y. Yagodzinskyy, A. Toivonen, and H. Hanninen ). Author Index. Subject Index.
