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

Front Matter ....Pages i-xxxvii
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
Front Matter ....Pages 1217-1217
 Simultaneous Thermal and Gamma Radiation Aging of Electrical Cable Polymers  (Leonard S. Fifield)....Pages 1219-1226
 Principal Component Analysis (PCA) as a Statistical Tool for Identifying Key Indicators of Nuclear Power Plant Cable Insulation Degradation  (Chamila C. De Silva, Scott P. Beckman, Shuaishuai Liu, Nicola Bowler)....Pages 1227-1239
 How Can Material Characterization Support Cable Aging Management?  (David Rouison, Marzieh Riahinezhad, Anand Anandakumaran)....Pages 1241-1256
 Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants  (R. C. Duckworth, A. Ellis, B. Hinderliter, E. Hill, M. Maurer-Jones)....Pages 1257-1265
 Frequency Domain Reflectometry Modeling and Measurement for Nondestructive Evaluation of Nuclear Power Plant Cables  (S. W. Glass, L. S. Fifield, A. M. Jones, T. S. Hartman)....Pages 1267-1280
 Aging Mechanisms and Nondestructive Aging Indicator of Filled Cross-Linked Polyethylene (XLPE) Exposed to Simultaneous Thermal and Gamma Radiation  (Shuaishuai Liu, Leonard S. Fifield, Nicola Bowler)....Pages 1281-1291
 Successful Detection of Insulation Degradation in Cables by Frequency Domain Reflectometry  (Yoshimichi Ohki, Naoshi Hirai)....Pages 1293-1301
 Capacitive Nondestructive Evaluation of Aged Cross-Linked Polyethylene (XLPE) Cable Insulation Material  (Z. H. Shao, N. Bowler)....Pages 1303-1313
 Tracking of Nuclear Cable Insulation Polymer Structural Changes Using the Gel Fraction and Uptake Factor Method  (Miguel Correa, Qian Huang, Leonard S. Fifield)....Pages 1315-1321
 Degradation of Silicone Rubber Analyzed by Instrumental Analyses and Dielectric Spectroscopy  (Yoshimichi Ohki, Naoshi Hirai, Daomin Min, Liuqing Yang, Shengtao Li)....Pages 1323-1332
Front Matter ....Pages 1333-1333
 Automated Detection of Alkali-Silica Reaction in Concrete Using Linear Array Ultrasound Data  (Dwight A. Clayton, Hector Santos-Villalobos, N. Dianne Bull Ezell, Joseph Clayton, Justin Baba)....Pages 1335-1345
 Coupled Physics Simulation of Expansive Reactions in Concrete with the Grizzly Code  (Benjamin W. Spencer, Hai Huang)....Pages 1347-1357
 Overview of EPRI Long Term Operations Work on Nuclear Power Plant Concrete Structures  (Joe Wall, Sam Johnson)....Pages 1359-1365
 The Effects of Neutron Irradiation on the Mechanical Properties of Mineral Analogues of Concrete Aggregates  (Thomas M. Rosseel, Maxim N. Gussev, Luis F. Mora)....Pages 1367-1377
Front Matter ....Pages 1379-1379
 Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization  (Kevin G. Field, Yukinori Yamamoto, Bruce A. Pint, Maxim N. Gussev, Kurt A. Terrani)....Pages 1381-1389
 Interdiffusion Behavior of FeCrAl with U3Si2  (Rita E. Hoggan, Lingfeng He, Jason M. Harp)....Pages 1391-1400
 Mechanical Behavior of FeCrAl and Other Alloys Following Exposure to LOCA Conditions Plus Quenching  (Evan J. Dolley, Michael Schuster, Cole Crawford, Raul B. Rebak)....Pages 1401-1416
 Mechanical Behavior and Structure of Advanced Fe-Cr-Al Alloy Weldments  (M. N. Gussev, K. G. Field, E. Cakmak, Y. Yamamoto)....Pages 1417-1430
 Investigating Potential Accident Tolerant Fuel Cladding Materials and Coatings  (K. Daub, S. Y. Persaud, R. B. Rebak, R. Van Nieuwenhove, S. Ramamurthy, H. Nordin)....Pages 1431-1450
 Steam Oxidation Behavior of FeCrAl Cladding  (B. A. Pint, K. A. Terrani, R. B. Rebak)....Pages 1451-1460
 In-Situ Proton Irradiation-Corrosion Study of ATF Candidate Alloys in Simulated PWR Primary Water  (Peng Wang, Gary S. Was)....Pages 1461-1474
 Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings  (Stephen S. Raiman, Caen Ang, Peter Doyle, Kurt A. Terrani)....Pages 1475-1483
 Characterization of the Hydrothermal Corrosion Behavior of Ceramics for Accident Tolerant Fuel Cladding  (Peter J. Doyle, Stephen S. Raiman, R. Rebak, Kurt A. Terrani)....Pages 1485-1496
 Corrosion of Multilayer Ceramic-Coated ZIRLO Exposed to High Temperature Water  (Kiran K. Mandapaka, Gary S. Was)....Pages 1497-1508
Front Matter ....Pages 1509-1509
 Calibration of the Local IGSCC Engineering Model for Alloy 600  (Thierry Couvant, Jacqueline Caballero, Cécilie Duhamel, Jérôme Crépin, Takaharu Maeguchi)....Pages 1511-1533
 Prediction of IGSCC as a Finite Element Modeling Post-analysis  (Thierry Couvant)....Pages 1535-1550
 Monte Carlo Simulation Based on SCC Test Results in Hydrogenated Steam Environment for Alloy 600  (Yohei Sakakibara, Ippei Shinozaki, Gen Nakayama, Takashi Nan-Nichi, Tomoyuki Fujii, Yoshinobu Shimamura et al.)....Pages 1551-1561
 Protection of the Steel Used for Dry Cask Storage System from Atmospheric Corrosion by Tio2 Coating  (Jing-Ru Yang, Mei-Ya Wang, Tsung-Kuang Yeh, Peter Chen)....Pages 1563-1571
 Predictive Modeling of Baffle-Former Bolt Failures in Pressurized Water Reactors  (Gregory A. Banyay, Matthew H. Kelley, Joshua K. McKinley, Matthew J. Palamara, Scott E. Sidener, Clarence L. Worrell)....Pages 1573-1588
 Technical Basis and SCC Growth Rate Data to Develop an SCC Disposition Curve for Alloy 82 in BWR Environments  (Katsuhiko Kumagai, Yusuke Sakai, Takayuki Kaminaga)....Pages 1589-1603
Front Matter ....Pages 1605-1605
 SCC and Fracture Toughness of XM-19  (Peter Andresen, Martin Morra, Robert Carter)....Pages 1607-1622
 On the Effect of Preoxidation of Nickel Alloy X-750  (Silvia Tuzi, Kenneth Göransson, Fang Liu, Mattias Thuvander, Krystyna Stiller)....Pages 1623-1632
 Microstructures of Oxide Films Formed in Alloy 182 BWR Core Shroud Support Leg Cracks  (Jiaxin Chen, Daniel Jädernäs, Fredrik Lindberg, Henrik Pettersson, Martin Bjurman, Kwadwo Kese et al.)....Pages 1633-1647
 Effect of Chloride Transients on Crack Growth Rates in Low Alloy Steels in BWR Environments  (Xiaoyuan Lou, Raj Pathania)....Pages 1649-1661
 Electrochemical Behavior of Platinum Treated Type 304 Stainless Steels in Simulated BWR Environments Under Startup Conditions  (Chu-Yung Yuan, Tsung-Kuang Yeh, Mei-Ya Wang)....Pages 1663-1672
 Investigations of the Dual Benefits of Zinc Injection on Cobalt-60 Uptake and Oxide Film Formation Under Boiling Water Reactor Conditions  (Samuel Holdsworth, Fabio Scenini, M. Grace Burke, Tsuyoshi Ito, Yoichi Wada, Hideyuki Hosokawa et al.)....Pages 1673-1683
 SCC Mitigation in Boiling Water Reactors: Platinum Deposition and Durability on Structural Materials  (Pascal V. Grundler, Stefan Ritter, Lyubomira Veleva)....Pages 1685-1700
 Confirmation of On-Line NobleChem™ (OLNC) Mitigation Effectiveness in Operating Boiling Water Reactors (BWRs)  (Joe Kopcash, Juan Varela, Hubert Huie, G. Depta)....Pages 1701-1712
 Development of the Fundamental Multiphysics Analysis Model for Crevice Corrosion Using a Finite Element Method  (Masahiko Tachibana, Yoichi Wada, Takayuki Arakawa, Yoshiharu Kikuchi, Takehiro Seto)....Pages 1713-1723
 In Situ Electrochemical Study on Crevice Environment of Stainless Steel in High Temperature Water  (Y. Soma, C. Kato, F. Ueno)....Pages 1725-1737
Front Matter ....Pages 1739-1739
 Corrosion Fatigue Crack Initiation in Zr-2.5Nb  (H. M. Nordin, A. J. Phillion, T. M. Karlsen, S. Persaud)....Pages 1741-1757
 Cluster Dynamics Model for the Hydride Precipitation Kinetics in Zirconium Cladding  (Donghua Xu, Hang Xiao)....Pages 1759-1768
 Modeling Corrosion Kinetics of Zirconium Alloys in Loss-of-Coolant Accident (LOCA)  (Léo Borrel, Adrien Couet)....Pages 1769-1779
 Progressing Zirconium-Alloy Corrosion Models Using Synchrotron XANES  (Michael Moorehead, Adrien Couet, Jing Hu, Zhonghou Cai)....Pages 1781-1792
 Advanced Characterization of Hydrides in Zirconium Alloys  (S. M. Hanlon, S. Y. Persaud, F. Long, M. R. Daymond)....Pages 1793-1813
 Influence of Alloying Elements and Effect of Stress on Anisotropic Hydrogen Diffusion in Zr-Based Alloys Predicted by Accelerated Kinetic Monte Carlo Simulations  (Jianguo Yu, Chao Jiang, Yongfeng Zhang)....Pages 1815-1826
Front Matter ....Pages 1827-1827
 Influence of δ-Ferrite Content on Thermal Aging Induced Mechanical Property Degradation in Cast Stainless Steels  (Thak Sang Byun, Timothy G. Lach, Ying Yang, Changheui Jang)....Pages 1829-1840
 Microstructure and Deformation Behavior of Thermally Aged Cast Austenitic Stainless Steels  (Y. Chen, C. Xu, X. Zhang, W.-Y. Chen, J.-S. Park, J. Almer et al.)....Pages 1841-1857
 Microstructural Evolution of Cast Austenitic Stainless Steels Under Accelerated Thermal Aging  (Timothy G. Lach, Thak Sang Byun)....Pages 1859-1868
 Electrochemical Characteristics of Delta Ferrite in Thermally Aged Austenitic Stainless Steel Weld  (Gokul Obulan Subramanian, Sunghoon Hong, Ho Jung Lee, Byeong Seo Kong, Kyoung-Soo Lee, Thak Sang Byun et al.)....Pages 1869-1877
 Effect of Long-Term Thermal Aging on SCC Initiation Susceptibility in Low Carbon Austenitic Stainless Steels  (So Aoki, Keietsu Kondo, Yoshiyuki Kaji, Masahiro Yamamoto)....Pages 1879-1888
 Crack Growth Rate and Fracture Toughness of CF3 Cast Stainless Steels at ~3 DPA  (Y. Chen, W.-Y. Chen, B. Alexandreanu, K. Natesan, A. S. Rao)....Pages 1889-1903
 Effects of Thermal Aging and Low Dose Neutron Irradiation on the Ferrite Phase in a 308L Weld  (Z. Li, Y. Chen, A. S. Rao, Y. Yang)....Pages 1905-1918
 Microstructural Evolution of Welded Stainless Steels on Integrated Effect of Thermal Aging and Low Flux Irradiation  (Martin Bjurman, Kristina Lindgren, Mattias Thuvander, Peter Ekström, Pål Efsing)....Pages 1919-1926
Front Matter ....Pages 1927-1927
 The Use of Tapered Specimens to Evaluate the SCC Initiation Susceptibility in Alloy 182 in BWR and PWR Environments  (Juxing Bai, Stefan Ritter, Hans-Peter Seifert, Marc Vankeerberghen, Rik-Wouter Bosch)....Pages 1929-1948
 Effect of Thermal Aging on Fracture Mechanical Properties and Crack Propagation Behavior of Alloy 52 Narrow-Gap Dissimilar Metal Weld  (Matias Ahonen, Sebastian Lindqvist, Teemu Sarikka, Jari Lydman, Roman Mouginot, Ulla Ehrnstén et al.)....Pages 1949-1963
 Distribution and Characteristics of Oxide Films Formed on Stainless Steel Cladding on Low Alloy Steel in Simulated PWR Primary Water Environments  (Qi Xiong, Hongjuan Li, Zhanpeng Lu, Junjie Chen, Qian Xiao, Jiarong Ma et al.)....Pages 1965-1978
 Microstructural Characterization of Alloy 52 Narrow-Gap Dissimilar Metal Weld After Aging  (Teemu Sarikka, Roman Mouginot, Matias Ahonen, Sebastian Lindqvist, Ulla Ehrnstén, Pekka Nevasmaa et al.)....Pages 1979-1993
 A Statistical Analysis on Modeling Uncertainty Through Crack Initiation Tests  (Jae Phil Park, Chanseok Park, Chi Bum Bahn)....Pages 1995-2011
Front Matter ....Pages 2013-2013
 Laboratory Analysis of a Leaking Letdown Cooler from Oconee Unit 3  (James Hyres, Rocky Thompson, Jim Batton)....Pages 2015-2034
 Root Cause Analysis of Cracking in Alloy 182 BWR Core Shroud Support Leg Cracks  (Martin Bjurman, Daniel Jädernäs, Kwadwo Kese, Anders Jenssen, Jiaxin Chen, Massimo Cocco et al.)....Pages 2035-2045
 Microbially Induced Corrosion in Firefighting Systems—Experience and Remedies  (Ulla Ehrnstén, Leena Carpén, Kimmo Tompuri)....Pages 2047-2056
 Managing the Ageing Degradation of Concealed Safety Relevant Cooling Water Piping in European S/KWU LWRs  (Martin Widera, Gerd Ahlers, Bernd Gruhne, Thomas Wermelinger)....Pages 2057-2068
 Identification of PWR Stainless Steel Piping Safety Significant Locations Susceptible to Stress Corrosion Cracking  (R. Hosler, A. Kulp, P. Stevenson, S. Petro)....Pages 2069-2094
Front Matter ....Pages 2095-2095
 On the Use of Density-Based Algorithms for the Analysis of Solute Clustering in Atom Probe Tomography Data  (Emmanuelle A. Marquis, Vicente Araullo-Peters, Yan Dong, Auriane Etienne, Svetlana Fedotova, Katsuhiko Fujii et al.)....Pages 2097-2113
 Comparative Study on Short Time Oxidation of Un-Irradiated and Protons Pre-Irradiated 316L Stainless Steel in Simulated PWR Water  (M. Boisson, L. Legras, F. Carrette, O. Wendling, T. Sauvage, A. Bellamy et al.)....Pages 2115-2134
 Hydrogen Trapping by Irradiation-Induced Defects in 316L Stainless Steel  (Anne-Cécile Bach, Frantz Martin, Cécilie Duhamel, Stéphane Perrin, François Jomard, Jérôme Crépin)....Pages 2135-2151
 Grain Boundary Oxidation of Neutron Irradiated Stainless Steels in Simulated PWR Water  (Takuya Fukumura, Koji Fukuya, Katsuhiko Fujii, Terumitsu Miura, Yuji Kitsunai)....Pages 2153-2163
 Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments—Part I: Microstructure Characterization  (M. Song, M. Wang, G. S. Was, L. Nelson, R. Pathania)....Pages 2165-2176
 Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking  (Mi Wang, Miao Song, Gary S. Was, L. Nelson, R. Pathania)....Pages 2177-2188
 Solute Clustering in As-irradiated and Post-irradiation-Annealed 304 Stainless Steel  (Yimeng Chen, Yan Dong, Emmanuelle Marquis, Zhijie Jiao, Justin Hesterberg, Gary Was et al.)....Pages 2189-2207
Front Matter ....Pages 2209-2209
 Irradiation-Assisted Stress Corrosion Cracking Initiation Screening Criteria for Stainless Steels in PWR Systems  (Steve Fyfitch, Sarah Davidsaver, Kyle Amberge)....Pages 2211-2220
 Novel Technique for Quantitative Measurement of Localized Stresses Near Dislocation Channel—Grain Boundary Interaction Sites in Irradiated Stainless Steel  (D. C. Johnson, G. S. Was)....Pages 2221-2229
 IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation Annealing  (Justin R. Hesterberg, Zhijie Jiao, Gary S. Was)....Pages 2231-2242
 Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 Exposed to BWR Environments  (S. Teysseyre, J. H. Jackson, P. L. Andresen, P. Chou, B. Carter)....Pages 2243-2253
 Evaluation of Crack Growth Rates and Microstructures Near the Crack Tip of Neutron-Irradiated Austenitic Stainless Steels in Simulated BWR Environment  (Yasuhiro Chimi, Shigeki Kasahara, Hitoshi Seto, Yuji Kitsunai, Masato Koshiishi, Yutaka Nishiyama)....Pages 2255-2270
 Effect of Specimen Size on the Crack Growth Rate Behavior of Irradiated Type 304 Stainless Steel  (A. Jenssen, P. Chou, C. Tobpasi)....Pages 2271-2288
 Plastic Deformation Processes Accompanying Stress Corrosion Crack Propagation in Irradiated Austenitic Steels  (M. N. Gussev, G. S. Was, J. T. Busby, K. J. Leonard)....Pages 2289-2300
Front Matter ....Pages 2301-2301
 Effect of Grain Orientation on Irradiation Assisted Corrosion of 316L Stainless Steel in Simulated PWR Primary Water  (Rigel D. Hanbury, Gary S. Was)....Pages 2303-2312
 Finite Element Modelling to Investigate the Mechanisms of CRUD Deposition in PWR  (Jiejie Wu, Nicholas Stevens, Fabio Scenini, Brian Connolly, Andy Banks, Andrew Powell et al.)....Pages 2313-2325
 Properties of Oxide Films on Ni–Cr–xFe Alloys in a Simulated PWR Water Environment  (Xiangkun Ru, Zhanpeng Lu, Junjie Chen, Guangdong Han, Jinlong Zhang, Pengfei Hu et al.)....Pages 2327-2342
Front Matter ....Pages 2343-2343
 Effect of Applied Potential and Inhibitors on PbSCC of Alloy 690TT  (Brent Capell, Jesse Lumsden, Michael Calabrese, Rick Eaker)....Pages 2345-2360
 Corrosion of SG Tube Alloys in Typical Secondary Side Local Chemistries Derived from Operating Experience  (Ian de Curieres)....Pages 2361-2379
 Investigation on the Effect of Lead (Pb) on the Degradation Behavior of Passive Films on Alloy 800  (J. Ulaganathan, H. Ha)....Pages 2381-2397
 Influence of Alloying on α-αʹ Phase Separation in Duplex Stainless Steels  (David A. Garfinkel, Jonathan D. Poplawsky, Wei Guo, George A. Young, Julie D. Tucker)....Pages 2399-2408
 Stress Corrosion Cracking of Alloy 800 in Secondary Side Crevice Environment  (Maria-Lynn Komar, Guylaine Goszczynski)....Pages 2409-2419
 Using Modern Microscopy to “Fingerprint” Secondary Side SCC in Ni–Fe Alloys  (S. Y. Persaud, J. M. Smith, C. D. Judge, M. Bryk, R. C. Newman, M. G. Burke et al.)....Pages 2421-2451
Back Matter ....Pages 2453-2532