Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors: Volume 1

Description

This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems. Front Matter ....Pages i-xxix Front Matter ....Pages 1-1 Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and Variant Weld Material (Amanda R. Jenks, Glenn A. White, Paul Crooker)....Pages 3-14 Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components (Warren Bamford, Steve Fyfitch, Raj Pathania, Paul Crooker)....Pages 15-25 SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water (Peter L. Andresen, Martin M. Morra, Kawaljit Ahluwalia)....Pages 27-53 NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys (Greg Oberson, Margaret Audrain, Jay Collins, Eric Reichelt)....Pages 55-65 Stress Corrosion Cracking of Alloy 52/152 Weldments Near Dissimilar Metal Weld Interfaces (B. Alexandreanu, Y. Chen, W. -Y. Chen, K. Natesan)....Pages 67-85 Stress Corrosion Crack Growth Rate Testing of Composite Material Specimens (David S. Morton, John V. Mullen, Eric Plesko, John Sutliff, Robert Morris, Nathan Lewis)....Pages 87-103 Investigation of Hydrogen Behavior in Relation to the PWSCC Mechanism in Alloy TT690 (Takumi Terachi, Takuyo Yamada, Nobuo Totsuka, Koji Arioka)....Pages 105-118 Front Matter ....Pages 119-119 Crack Initiation of Alloy 600 in PWR Water (Peter Andresen, Peter Chou)....Pages 121-135 SCC Initiation Behavior of Alloy 182 in PWR Primary Water (Mychailo Toloczko, Ziqing Zhai, Stephen Bruemmer)....Pages 137-160 Multiple Cracks Interactions in Stress Corrosion Cracking: In Situ Observation by Digital Image Correlation and Phase Field Modeling (J. Bolivar, T.T. Nguyen, Y. Shi, M. Fregonese, J. Réthoré, J. Adrien et al.)....Pages 161-174 Stress Corrosion Cracking Initiation of Alloy 82 in Hydrogenated Steam (E. Chaumun, J. Crépin, C. Duhamel, C. Guerre, E. Héripré, M. Sennour et al.)....Pages 175-189 Application of Ultra-High Pressure Cavitation Peening on Reactor Vessel Head Penetration, BMN and Primary Nozzles (Daniel Brimbal, Gary Poling, Darren Wood, Antoine Marion, Nicolas Huin, Olivier Calonne)....Pages 191-201 The Effect of Surface Condition on Primary Water Stress Corrosion Cracking Initiation of Alloy 600 (S. R. Pemberton, M. A. Chatterton, A. S. Griffiths, S. L. Medway, D. R. Tice, K. J. Mottershead)....Pages 203-216 Microstructural Effects on SCC Initiation in PWR Primary Water for Cold-Worked Alloy 600 (Ziqing Zhai, Mychailo Toloczko, Stephen Bruemmer)....Pages 217-229 Front Matter ....Pages 231-231 A Kinetic Study of Order-Disorder Transition in Ni–Cr Based Alloys (B. Stephan, D. Jacob, F. Delabrouille, L. Legras)....Pages 233-249 The Role of Stoichiometry on Ordering Phase Transformations in Ni–Cr Alloys for Nuclear Applications (Fei Teng, Li-Jen Yu, Octav Ciuca, Emmanuelle Marquis, Grace Burke, Julie D. Tucker)....Pages 251-259 The Effect of Hardening via Long Range Order on the SCC and LTCP Susceptibility of a Nickel-30Chromium Binary Alloy (Tyler E. Moss, Catherine M. Brown, George A. Young)....Pages 261-279 PWSCC Initiation of Alloy 600: Effect of Long-Term Thermal Aging and Triaxial Stress (Seung Chang Yoo, Kyoung Joon Choi, Seunghyun Kim, Ji-Soo Kim, Byoung Ho Choi, Yun-Jae Kim et al.)....Pages 281-292 Stress Corrosion Cracking Behavior of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water (Mi Wang, Miao Song, Gary S. Was, L. Nelson)....Pages 293-305 Time- and Fluence-to-fracture Studies of Alloy 718 in Reactor (C. Joseph Long)....Pages 307-320 Development of Short-Range Order and Intergranular Carbide Precipitation in Alloy 690 TT upon Thermal Ageing (Roman Mouginot, Teemu Sarikka, Mikko Heikkilä, Mykola Ivanchenko, Unto Tapper, Ulla Ehrnstén et al.)....Pages 321-334 Front Matter ....Pages 335-335 Diffusion Processes as Possible Mechanisms for Cr Depletion at SCC Crack Tip (Josiane Nguejio, Jérôme Crépin, Cécilie Duhamel, Fabrice Gaslain, Catherine Guerre, François Jomard et al.)....Pages 337-357 Role of Grain Boundary Cr5B3 Precipitates on Intergranular Attack in Alloy 600 (Daniel K. Schreiber, Matthew J. Olszta, Karen Kruska, Stephen M. Bruemmer)....Pages 359-374 Advanced Characterization of Oxidation Processes and Grain Boundary Migration in Ni Alloys Exposed to 480 °C Hydrogenated Steam (S. Y. Persaud, B. Langelier, A. Eskandari, H. Zhu, G. A. Botton, R. C. Newman)....Pages 375-398 Exploring Nanoscale Precursor Reactions in Alloy 600 in H2/N2–H2O Vapor Using In Situ Analytical Transmission Electron Microscopy (M. G. Burke, G. Bertali, F. Scenini, S. J. Haigh, E. Prestat)....Pages 399-407 Electrochemical and Microstructural Characterization of Alloy 600 in Low Pressure H2-Steam (L. Volpe, G. Bertali, M. Curioni, M. G. Burke, F. Scenini)....Pages 409-422 Effect of Dissolved Hydrogen on the Crack Growth Rate and Oxide Film Formation at the Crack Tip of Alloy 600 Exposed to Simulated PWR Primary Water (Johan Stjärnsäter, Jiaxin Chen, Fredrik Lindberg, Peter Ekström, Pål Efsing)....Pages 423-437 A Mechanistic Study of the Effect of Temperature on Crack Propagation in Alloy 600 Under PWR Primary Water Conditions (Zhao Shen, Sergio Lozano-Perez)....Pages 439-454 Front Matter ....Pages 455-455 Grain Boundary Damage Evolution and SCC Initiation of Cold-Worked Alloy 690 in Simulated PWR Primary Water (Ziqing Zhai, Mychailo Toloczko, Karen Kruska, Daniel Schreiber, Stephen Bruemmer)....Pages 457-483 PWSCC Susceptibility of Alloy 690, 52 and 152 (Takaharu Maeguchi, Kimihisa Sakima, Kenji Sato, Koji Fujimoto, Yasuto Nagoshi, Kazuya Tsutsumi)....Pages 485-500 Relationship Among Dislocation Density, Local Strain Distribution, and PWSCC Susceptibility of Alloy 690 (Tae-Young Ahn, Sung-Woo Kim, Seong Sik Hwang, Hong-Pyo Kim)....Pages 501-507 Morphology Evolution of Grain Boundary Carbides Precipitated Near Triple Junctions in Highly Twinned Alloy 690 (Hui Li, Xirong Liu, Kai Zhang, Wenqing Liu, Shuang Xia)....Pages 509-517 A Mechanistic Study of Stress Corrosion Crack Propagation in Heavily Cold Worked TT Alloy 690 Exposed to Simulated PWR Primary Water (Toshio Yonezawa, Masashi Watanabe, Atsushi Hashimoto)....Pages 519-534 Microstructural Study on the Stress Corrosion Cracking of Alloy 690 in Simulated Pressurized Water Reactor Primary Environment (Wenjun Kuang, Miao Song, Chad M. Parish, Gary S. Was)....Pages 535-545 Front Matter ....Pages 547-547 Effect of Strain Rate and High Temperature Water on Deformation Structure of VVER Neutron Irradiated Core Internals Steel (Anna Hojna, Jan Duchon, Patricie Halodova, Hygreeva Kiran Namburi)....Pages 549-563 Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts (Jan Michalička, Zhijie Jiao, Gary Was)....Pages 565-580 In Situ and Ex Situ Observations of the Influence of Twin Boundaries on Heavy Ion Irradiation Damage Effects in 316L Austenitic Stainless Steels (G. Meric de Bellefon, J. C. van Duysen, K. Sridharan)....Pages 581-591 In Situ Microtensile Testing for Ion Beam Irradiated Materials (H. T. Vo, A. Reinhardt, D. Frazer, N. Bailey, P. Chou, P. Hosemann)....Pages 593-603 Development of High Irradiation Resistant and Corrosion Resistant Oxide Dispersion Strengthened Austenitic Stainless Steels (Takahiro Ishizaki, Yusaku Maruno, Kiyohiro Yabuuchi, Sosuke Kondo, Akihiko Kimura)....Pages 605-615 Spherical Nanoindentation Stress-Strain Analysis of Ion-Irradiated Tungsten (Siddhartha Pathak, Jordan S. Weaver, Cheng Sun, Yongqiang Wang, Surya R. Kalidindi, Nathan A. Mara)....Pages 617-635 Front Matter ....Pages 637-637 Formation of He Bubbles by Repair-Welding in Neutron-Irradiated Stainless Steels Containing Surface Cold-Worked Layer (Masato Koshiishi, Naoto Shigenaka)....Pages 639-650 Predictions and Measurements of Helium and Hydrogen in PWR Structural Components Following Neutron Irradiation and Subsequent Charged Particle Bombardment (F. A. Garner, L. Shao, C. Topbasi)....Pages 651-668 Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation (C. Sun, L. Malerba, M. J. Konstantinovic, F. A. Garner, S. A. Maloy)....Pages 669-680 Carbon Contamination, Its Consequences and Its Mitigation in Ion-Simulation of Neutron-Induced Swelling of Structural Metals (Lin Shao, Jonathan Gigax, Hyosim Kim, Frank A. Garner, Jing Wang, Mychailo B. Toloczko)....Pages 681-693 Void Swelling Screening Criteria for Stainless Steels in PWR Systems (Sarah Davidsaver, Steve Fyfitch, Daniel Brimbal, Joshua McKinley, Kyle Amberge)....Pages 695-708 Theoretical Study of Swelling of Structural Materials in Light Water Reactors at High Fluencies (S. I. Golubov, A. V. Barashev)....Pages 709-723 Front Matter ....Pages 725-725 High Resolution Transmission Electron Microscopy of Irradiation Damage in Inconel X-750 (C. D. Judge, H. Rajakumar, A. Korinek, G. Botton, J. Cole, J. W. Madden et al.)....Pages 727-741 In Situ SEM Push-to-Pull Micro-tensile Testing of Ex-service Inconel X-750 (C. Howard, C. D. Judge, H. T. Vo, M. Griffiths, P. Hosemann)....Pages 743-757 Microstructural Characterization of Proton-Irradiated 316 Stainless Steels by Transmission Electron Microscopy and Atom Probe Tomography (Yun Soo Lim, Dong Jin Kim, Seong Sik Hwang)....Pages 759-772 Front Matter ....Pages 773-773 Microstructural Effects on Stress Corrosion Initiation in Austenitic Stainless Steel in PWR Environments (D. R. Tice, V. Addepalli, K. J. Mottershead, M. G. Burke, F. Scenini, S. Lozano-Perez et al.)....Pages 775-792 Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water (F. Scenini, J. Lindsay, Litao Chang, Y. L. Wang, M. G. Burke, S. Lozano-Perez et al.)....Pages 793-810 SCC Initiation in the Machined Austenitic Stainless Steel 316L in Simulated PWR Primary Water (Litao Chang, Jonathan Duff, M. Grace Burke, Fabio Scenini)....Pages 811-827 High-Resolution Characterisation of Austenitic Stainless Steel in PWR Environments: Effect of Strain and Surface Finish on Crack Initiation and Propagation (G. Pimentel, D. R. Tice, V. Addepalli, K. J. Mottershead, M. G. Burke, F. Scenini et al.)....Pages 829-847 SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions (Nicolas Huin, Olivier Calonne, Matthias Herbst, Renate Kilian)....Pages 849-863 SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions (Matthias Herbst, Renate Kilian, Nicolas Huin, Olivier Calonne)....Pages 865-880 The Effect of Microchemistry on the Crack Response of Lightly Cold Worked Dual Certified Type 304/304L Stainless Steel After Sensitizing Heat Treatment (K. B. Fisher, B. D. Miller, E. C. Johns, R. Hermer, C. Brown, E. A. Marquis)....Pages 881-891 Front Matter ....Pages 893-893 The Effect of Load Ratio on the Fatigue Crack Growth Rate of Type 304 Stainless Steels in Air and High Temperature Deaerated Water at 482 °F (D. J. Paraventi, C. M. Brown, L. B. O’Brien, B. A. McGraw)....Pages 895-911 Electrical Potential Drop Observations of Fatigue Crack Closure (E. A. West)....Pages 913-925 The Effect of Environment and Material Chemistry on Single-Effects Creep Testing of Austenitic Stainless Steels (L. B. O’Brien, B. D. Miller)....Pages 927-942 Corrosion Fatigue Behavior of Austenitic Stainless Steel in a Pure D2O Environment (L. Yu, R. G. Ballinger, X. Huang, M. M. Morra, L. B. O’Brien, D. J. Paraventi et al.)....Pages 943-956 Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments (S. L. Medway, D. R. Tice, N. Platts, A. Griffiths, G. Ilevbare, R. Pathania)....Pages 957-986 Study on Hold-Time Effects in Environmental Fatigue Lifetime of Low-Alloy Steel and Austenitic Stainless Steel in Air and Under Simulated PWR Primary Water Conditions (M. Herbst, A. Roth, J. Rudolph)....Pages 987-1006 Front Matter ....Pages 1007-1007 Evaluation of Additively Manufactured Materials for Nuclear Plant Components (R. M. Horn, M. Connor, D. Webber, J. Jackson, F. Bolger)....Pages 1009-1020 Hot Cell Tensile Testing of Neutron Irradiated Additively Manufactured Type 316L Stainless Steel (Paula D. Freyer, William T. Cleary, Elaine M. Ruminski, C. Joseph Long, Peng Xu)....Pages 1021-1038 Computational and Experimental Studies on Novel Materials for Fission Gas Capture (Shenli Zhang, Haoyan Sha, Erick Yu, Maria Perez Page, Ricardo Castro, Pieter Stroeve et al.)....Pages 1039-1050 Hydrogen Assisted Cracking Studies of a 12% Chromium Martensitic Stainless Steel—Influence of Hardness, Stress and Environment (D. A. Horner, M. Lowden, P. Nevitt, G. Quirk)....Pages 1051-1065 Investigation of Flow Accelerated Corrosion Models to Predict the Corrosion Behavior of Coated Carbon Steels in Secondary Piping Systems (Seunghyun Kim, Ji Hyun Kim)....Pages 1067-1076 Effect of High-Temperature Water Environment on the Fracture Behaviour of Low-Alloy RPV Steels (Z. Que, H. P. Seifert, P. Spätig, G. S. Rao, S. Ritter)....Pages 1077-1099 Corrosion Fatigue Testing of Low Alloy Steel in Water Environment with Low Levels of Oxygen and Varied Load Dwell Times (Cybele Gabris)....Pages 1101-1108 Feasibility Study of the Internal Zr/ZrO2 Reference Electrodes in Supercritical Water Environments (Yu-Hsuan Li, Yu-Ming Tung, Tsung-Kuang Yeh, Mei-Ya Wang)....Pages 1109-1122 Front Matter ....Pages 1123-1123 Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation (D. A. Merezhko, M. S. Merezhko, M. N. Gussev, J. T. Busby, O. P. Maksimkin, M. P. Short et al.)....Pages 1125-1140 Quantifying Erosion-Corrosion Impacts on Light Water Reactor Piping (C. E. Guzmán-Leong, J. W. Cluever, S. R. Gosselin)....Pages 1141-1156 Effect of Molybdate Anion Addition on Repassivation of Corroding Crevice in Austenitic Stainless Steel (Shun Watanabe, Tomohiro Sekiguchi, Hiroshi Abe, Yutaka Watanabe)....Pages 1157-1168 Effect of pH on Hydrogen Pick-Up and Corrosion in Zircaloy-4 (James Sayers, Susan Ortner, Kexue Li, Sergio Lozano-Perez)....Pages 1169-1180 Oxidation Kinetics of Austenitic Stainless Steels as SCWR Fuel Cladding Candidate Materials in Supercritical Water (Hiroshi Abe, Ryuichi Suzuki, Yutaka Watanabe)....Pages 1181-1194 A Recent Look at CANDU Feeder Cracking: High Resolution Transmission Electron Microscopy and Electron Energy Loss Near Edge Structure (ELNES) (C. D. Judge, S. Y. Persaud, A. Korinek, M. D. Wright)....Pages 1195-1215 Back Matter ....Pages 1217-1287