Environmental Degradation of Mat'ls in Nuclear Systems XII

Provided Courtesy of Materials Technology@TMS

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proc. 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, ed. T.R. Allen, P.J. King and L. Nelson, TMS, Warrendale, PA, 2005. | | | |
PAPER TITLE | AUTHOR(S) | PAGES | ABSTRACT | FULL PAPER | |
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Advances in Electrochemical Corrosion Potential Monitoring in Boiling Water Reactors | S. Hettiarachchi | 3-18 | View Abstract | Read the Full Paper | |
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 | 19-30 | View Abstract | Read the Full Paper | |

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

31-38

View Abstract

Read the Full Paper

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 | 39-47 | View Abstract | Read the Full Paper | |
The Initiation of Environmentally Assisted Cracking in BWR High Temperature Water | S. Wang, Y. Takeda, K. Sakaguchi, and T. Shoji | 49-55 | View Abstract | Read the Full Paper | |
Stress Corrosion Cracking of Type 316 and 316L Stainless Steels in High Temperature Water | N. Ishiyama, M. Mayuzumi, Y. Mizutani, and J.-i. Tani | 57-64 | View Abstract | Read the Full Paper | |
Crack Growth Behaviors of Low Carbon 316 Stainless Steels in 288°C Pure Water | M. Itow, M. Itatani, M. Kikuchi, and N. Tanaka | 65-70 | View Abstract | Read the Full Paper | |
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 | 73-85 | View Abstract | Read the Full Paper | |
Effects of Si on SCC of Irradiated and Unirradiated Stainless Steels and Nickel Alloys | P.L. Andresen, and M.M. Morra | 87-108 | View Abstract | Read the Full Paper | |
Stress Corrosion Crack Growth Behavior of Cold Worked Austenitic Stainless Steel in High Temperature Water | M. Tsubota, Y. Katayama, and Y. Saito | 109-115 | View Abstract | Read the Full Paper | |
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 | 117-123 | View Abstract | Read the Full Paper | |
The Electrochemistry of Boiling Water Reactors | H.S. Kim, M. Urquidi-Macdonald, and D. Macdonald | 125-132 | View Abstract | Read the Full Paper | |
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 | 135-142 | View Abstract | Read the Full Paper | |
Evaluation of the Fracture Research Institute Theoretical Stress Corrosion Cracking Model | E.D. Eason, R. Pathania, and T. Shoji | 145-153 | View Abstract | Read the Full Paper | |
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 | 157-165 | View Abstract | Read the Full Paper | |
Effects of Positive and Negative dK/da on SCC Growth Rates | P.L. Andresen, and M.M. Morra | 167-182 | View Abstract | Read the Full Paper | |
Evaluation of Stress Corrosion Crack Growth Rate Based on Inspection Data on Alloy 600 Tubing | Y. Garud, B. Woodman, and G. Boyers | 185-188 | View Abstract | Read the Full Paper | |
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 | 189-198 | View Abstract | Read the Full Paper | |
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 | 201-211 | View Abstract | Read the Full Paper | |
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 | 213-218 | View Abstract | Read the Full Paper | |
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 | 219-228 | View Abstract | Read the Full Paper | |
Transient Oxide Film Growth on Zirconium in High Temperature Aqueous Solutions | Y. Chen, M. Urquidi-Macdonald, and D.D. Macdonald | 229-237 | View Abstract | Read the Full Paper | |
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 | 241-254 | View Abstract | Read the Full Paper | |
Effect of Metallurgical Condition on Irradiation-Assisted Stress Corrosion Cracking of Commercial Stainless Steels | J.T. Busby, and G.S. Was | 255-265 | View Abstract | Read the Full Paper | |
Irradiation-Assisted Stress Corrosion Cracking of Heat-Affected Zones of Austenitic Stainless Steel Welds | R. Stoenescu, M.L. Castaño, S. van Dyck, A. Roth B. van der Schaaf, C. Ohms, and D. Gavillet | 267-276 | View Abstract | Read the Full Paper | |
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 | 277-287 | View Abstract | Read the Full Paper | |
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 | 289-298 | View Abstract | Read the Full Paper | |
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 | 299-310 | View Abstract | Read the Full Paper | |
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 | 311-318 | View Abstract | Read the Full Paper | |
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 | 319-326 | View Abstract | Read the Full Paper | |
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. Ehrnstén, W. Karlsen, P. Aaltonen, J-P. Massoud, and J-M. Boursier | 327-336 | View Abstract | Read the Full Paper | |
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. Høgberg | 337-348 | View Abstract | Read the Full Paper | |
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 | 349-356 | View Abstract | Read the Full Paper | |
Influence of the Neutron Spectrum on the Tensile Properties of Irradiated Austenitic Stainless Steels, in Air and in PWR Environment | J-P. Massoud, M. Žamboch, P. Brabec, V.K. Shamardin, V.I. Prokhorov, and Ph. Dubuisson | 357-364 | View Abstract | Read the Full Paper | |
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 | 365-378 | View Abstract | Read the Full Paper | |
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 | 379-388 | View Abstract | Read the Full Paper | |
Deformation Structure in 316 Stainless Steel Irradiated in a PWR | K. Fukuya, K. Fujii, and Y. Kitsunai | 389-394 | View Abstract | Read the Full Paper | |
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 | 395-402 | View Abstract | Read the Full Paper | |
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. Bréchet | 403-410 | View Abstract | Read the Full Paper | |
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 | 411-418 | View Abstract | Read the Full Paper | |
Microstructural Evolution in Neutron-Irradiated Stainless Steels: Comparison of LWR and Fast-Reactor Irradiations | D. Edwards, E. Simonen, S. Bruemmer, and P. Efsing | 419-428 | View Abstract | Read the Full Paper | |
Dose Rate Effects on Microchemistry and Microstructure Relevant to LWR Components | E.P. Simonen, D.J. Edwards, and S.M. Bruemmer | 429-438 | View Abstract | Read the Full Paper | |
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 | 439-448 | View Abstract | Read the Full Paper | |
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 | 449-456 | View Abstract | Read the Full Paper | |
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. | 459-470 | View Abstract | Read the Full Paper | |
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. Gómez-Briceño, J. Lapeña, M. Ernestová, M. Žamboch, U. Ehrnstén, J. Föhl, T. Weißenberg, H.-P. Seifert, and S. Ritter | 471-484 | View Abstract | Read the Full Paper | |
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 | 485-494 | View Abstract | Read the Full Paper | |
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 | 497-509 | View Abstract | Read the Full Paper | |
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 | 511-531 | View Abstract | Read the Full Paper | |
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 | 533-542 | View Abstract | Read the Full Paper | |
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 | 543-556 | View Abstract | Read the Full Paper | |
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 | 557-566 | View Abstract | Read the Full Paper | |
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 | 567-578 | View Abstract | Read the Full Paper | |
The Effect of Grain Orientation on the Cracking Behavior of Alloy 182 in PWR Environment | B. Alexandreanu, O.K. Chopra, and W.J. Shack | 579-588 | View Abstract | Read the Full Paper | |
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 | 589-600 | View Abstract | Read the Full Paper | |
Load Path Effects on the Fracture Toughness of Alloy 82H and 52 Welds in Low Temperature Water | C.M. Brown, and W.J. Mills | 601-612 | View Abstract | Read the Full Paper | |
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 | 613-622 | View Abstract | Read the Full Paper | |
Low Temperature Crack Propagation Evaluation in Pressurized Water Reactor Service | A. Demma, A. McIlree, and M. Herrera | 623-638 | View Abstract | Read the Full Paper | |
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. Kuniya | 639-650 | View Abstract | Read the Full Paper | |
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 | 651-660 | View Abstract | Read the Full Paper | |
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 | 661-668 | View Abstract | Read the Full Paper | |
Fracture Surface Morphology of Stress Corrosion Cracks in Nickel-Base Welds | W.J. Mills | 669-682 | View Abstract | Read the Full Paper | |
BWR SCC Mitigation Experiences with Hydrogen Water Chemistry | S. Hettiarachchi | 685-702 | View Abstract | Read the Full Paper | |
Effects of Bulk Water Chemistry on ECP Distribution Inside a Crevice | Y. Wada, K. Ishida, M. Tachibana, and M. Aizawa | 703-714 | View Abstract | Read the Full Paper | |
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 | 715-726 | View Abstract | Read the Full Paper | |
Online NobleChem Mitigation of SCC | P.L. Andresen, Y.J. Kim, T.P. Diaz, and S. Hettiarachchi | 727-744 | View Abstract | Read the Full Paper | |
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 | 745-753 | View Abstract | Read the Full Paper | |
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 | 755-761 | View Abstract | Read the Full Paper | |
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 | 763-770 | View Abstract | Read the Full Paper | |
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 | 773-784 | View Abstract | Read the Full Paper | |
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 | 785-794 | View Abstract | Read the Full Paper | |
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 | 795-802 | View Abstract | Read the Full Paper | |
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. Küster, E. Nowak, U. Wesseling, and M. Widera | 803-812 | View Abstract | Read the Full Paper | |
Root Cause Failure Analysis of Defected J-Groove Welds in Steam Generator Drainage Nozzles | P. Efsing, B. Forssgren, and R. Kilian | 813-819 | View Abstract | Read the Full Paper | |
Laboratory Investigation of the Stainless Steel Cladding on the Davis-Besse Reactor Vessel Head [ | H. Xu, S. Fyfitch, and J.W. Hyres | 821-831 | View Abstract | Read the Full Paper | |
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 | 833-842 | View Abstract | Read the Full Paper | |
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 | 843-853 | View Abstract | Read the Full Paper | |
Boric Acid Corrosion Laboratory Investigation of the Davis-Besse Reactor Pressure Vessel Head | H. Xu, S. Fyfitch, and J.W. Hyres | 855-862 | View Abstract | Read the Full Paper | |
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 | 863-870 | View Abstract | Read the Full Paper | |
The Role of Surface Films in the Stress Corrosion Cracking of Alloy 600 in PWR Primary Water | T.S. Mintz, and T.M. Devine | 873-881 | View Abstract | Read the Full Paper | |
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 | 883-890 | View Abstract | Read the Full Paper | |
Alloy Oxidation Studies Related to PWSCC | F. Scenini, R.C. Newman, R.A. Cottis, and R.J. Jacko | 891-902 | View Abstract | Read the Full Paper | |
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 | 903-911 | View Abstract | Read the Full Paper | |
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 | 913-924 | View Abstract | Read the Full Paper | |
Crack Initiation in Alloy 600 SG Tubing in Elevated pH PWR Primary Water | R.J. Jacko, and R.E. Gold | 925-936 | View Abstract | Read the Full Paper | |
Initiation of SCC in Alloy 600 Wrought Materials: A Laboratory and Statistical valuation | J. Daret | 937-945 | View Abstract | Read the Full Paper | |
SCC Initiation Testing of Nickel-Based Alloys Using In-Situ Monitored Uniaxial Tensile Specimens | E. Richey, D.S. Morton, and M.K. Schurman | 947-958 | View Abstract | Read the Full Paper | |
Cracking of Alloy 600 Nozzles and Welds in PWRs: Review of Cracking Events and Repair Service Experience [ | W. Bamford, and J. Hall | 959-966 | View Abstract | Read the Full Paper | |
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 | 967-975 | View Abstract | Read the Full Paper | |
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 | 977-988 | View Abstract | Read the Full Paper | |
Effects of PWR Primary Water Chemistry and Deaerated Water on SCC | P.L. Andresen, P.W. Emigh, M.M. Morra, and J. Hickling | 989-1008 | View Abstract | Read the Full Paper | |
Crack Growth Rates in Primary Side Materials in Elevated pH PWR Water | R.J. Jacko, and R.E. Gold | 1009-1018 | View Abstract | Read the Full Paper | |
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 | 1019-1028 | View Abstract | Read the Full Paper | |
SCC Growth Behavior of Austenitic Stainless Steels in PWR Primary Water Conditions | C. Guerre, O. Raquet, E. Herms, M. Le Calvar, and G. Turluer | 1029-1036 | View Abstract | Read the Full Paper | |
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 | 1037-1048 | View Abstract | Read the Full Paper | |
SCC of Cold-Worked Austenitic Stainless Steels in PWR Conditions | O. Raquet, E. Herms, F. Vaillant, T. Couvant, and J.-M. Boursier | 1049-1059 | View Abstract | Read the Full Paper | |
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 | 1061-1067 | View Abstract | Read the Full Paper | |
Effect of Strain-Hardening on Stress Corrosion Cracking of AISI 304L Stainless Steel in PWR Primary Environment at 360°C | K. Arioka, T. Yamada, T. Terachi, and G. Chiba | 1069-1081 | View Abstract | Read the Full Paper | |
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 | 1083-1089 | View Abstract | Read the Full Paper | |
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 | 1091-1099 | View Abstract | Read the Full Paper | |
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 | 1101-1110 | View Abstract | Read the Full Paper | |
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 | 1113-1123 | View Abstract | Read the Full Paper | |
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 | 1125-1130 | View Abstract | Read the Full Paper | |
Impurity Source Terms and Behavior in Nuclear Once-Through Steam Generators | R. Thompson | 1131-1142 | View Abstract | Read the Full Paper | |
Observations and Insights into Pb-Assisted Stress Corrosion Cracking of Alloy 600 Steam Generator Tubes | L.E. Thomas, and S.M. Bruemmer | 1143-1154 | View Abstract | Read the Full Paper | |
Modeling Concentrated Solution Transport and Accumulation in Steam Generator Tube Support Plate Crevices | A. Baum, and K. Evans | 1155-1162 | View Abstract | Read the Full Paper | |
Clues and Issues in the SCC of High Nickel Alloys Associated with Dissolved Lead | R.W. Staehle | 1163-1210 | View Abstract | Read the Full Paper | |
Effect of Lead Contamination on Steam Generator Tube Degradation | Y.C. Lu | 1211-1219 | View Abstract | Read the Full Paper | |

Effects of Pb on SCC of Alloy 600 and Alloy 690 in Prototypical Steam
Generator Chemistries

H. Radhakrishnan, R. Newman, and A. Carcea

1221-1228

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The Effect of Lead Ions on the Dissolution and Passivation of Nickel Base Alloys | J. Lumsden, A. McIlree, R. Eaker, R. Thompson and S. Slosnerick | 1229-1242 | View Abstract | Read the Full Paper | |

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

1243-1253

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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

1255-1266

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Effect of Water Chemistry on Corrosion Resistance of Alloy 600 SG Tubes Under
Acidic Conditions

S. Fukuchi, K. Koba, H. Anada, and M. Kanzaki

1267-1276

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SCC Behavior of Model Alloy 600 Containing Minor Element Cerium in a Caustic
Solutio

J.S. Kim, Y.-S. Yi, O.-C. Kwon, Y. Lim,
and M. Jung

1277-1284

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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

1285-1294

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Erosion-Corrosion of Alloy UNS N04400 | G. Ogundele, A. Lloyd, S. Pagan, and F. Camacho | 1295-1303 | View Abstract | Read the Full Paper | |

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

1305-1315

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Oxidation Behavior of Austenitic Materials Exposed to Secondary Side Water at 282°C | J. Sarver, and P. King | 1317-1325 | View Abstract | Read the Full Paper | |

Characterization of Austenitic Materials Exposed to Secondary Side Water at 282°C

S. Ramamurthy, R. Davidson, S. McIntyre,
J. Sarver, and P. King

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Challenges and Recent Progress in Corrosion and Stress Corosion Cracking of Alloys
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G.S. Was, and S. Teysseyre

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Effect of Proton Irradiation and Grain Boundary Engineering on Stress Corrosion
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G. Gupta, and G.S. Was

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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,
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A. Yilmazbayhan, and A.T. Motta

1369-1378

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Corrosion-Resistant Coatings for Use in a Supercritical Water Candu® Reactor

D.A. Guzonas, J.S. Wills, G.A. McRae, S. Sullivan, K. Chu,
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Corrosion and Stress Corrosion Cracking of Ferritic-Martensitic Alloys in
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Corrosion of Candidate Materials for Supercritical Water-Cooled Reactors

T.R. Allen, Y. Chen, L. Tan, X. Ren, K. Sridharan,
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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,
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Dynamic Strain Aging of Ni-Base Alloys Inconel 600 and 690

H. Hänninen, M. Ivanchenko, Y. Yagodzinskyy, V. Nevdacha,
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Stifling of Crevice Corrosion in Alloy 22 | K.G. Mon, G.M. Gordon, and R.B. Rebak | 1431-1438 | View Abstract | Read the Full Paper | |
Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository | K.G. Mon, and F. Hua | 1439-1456 | View Abstract | Read the Full Paper | |

SCC Initiation and Growth Rate Studies on Titanium Grade 7 and Base Metal, Welded
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P.L. Andresen, G.M. Catlin, P.W. Emigh,
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Dynamic Strain Ageing and EAC of Deformed Nitrogen-Alloyed AISI 316 Stainless
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U. Ehrnstén, M. Ivanchenko, V. Nevdacha, Y. Yagodzinskyy,
A. Toivonen, and H. Hänninen

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