Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors: Volume 2

Front Matter ....Pages i-xxix
Front Matter ....Pages 1-1
 Simultaneous Thermal and Gamma Radiation Aging of Electrical Cable Polymers  (Leonard S. Fifield)....Pages 3-10
 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 11-23
 How Can Material Characterization Support Cable Aging Management?  (David Rouison, Marzieh Riahinezhad, Anand Anandakumaran)....Pages 25-40
 Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants  (R. C. Duckworth, A. Ellis, B. Hinderliter, E. Hill, M. Maurer-Jones)....Pages 41-49
 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 51-64
 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 65-75
 Successful Detection of Insulation Degradation in Cables by Frequency Domain Reflectometry  (Yoshimichi Ohki, Naoshi Hirai)....Pages 77-85
 Capacitive Nondestructive Evaluation of Aged Cross-Linked Polyethylene (XLPE) Cable Insulation Material  (Z. H. Shao, N. Bowler)....Pages 87-97
 Tracking of Nuclear Cable Insulation Polymer Structural Changes Using the Gel Fraction and Uptake Factor Method  (Miguel Correa, Qian Huang, Leonard S. Fifield)....Pages 99-105
 Degradation of Silicone Rubber Analyzed by Instrumental Analyses and Dielectric Spectroscopy  (Yoshimichi Ohki, Naoshi Hirai, Daomin Min, Liuqing Yang, Shengtao Li)....Pages 107-116
Front Matter ....Pages 117-117
 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 119-129
 Coupled Physics Simulation of Expansive Reactions in Concrete with the Grizzly Code  (Benjamin W. Spencer, Hai Huang)....Pages 131-141
 Overview of EPRI Long Term Operations Work on Nuclear Power Plant Concrete Structures  (Joe Wall, Sam Johnson)....Pages 143-149
 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 151-161
Front Matter ....Pages 163-163
 Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization  (Kevin G. Field, Yukinori Yamamoto, Bruce A. Pint, Maxim N. Gussev, Kurt A. Terrani)....Pages 165-173
 Interdiffusion Behavior of FeCrAl with U3Si2  (Rita E. Hoggan, Lingfeng He, Jason M. Harp)....Pages 175-184
 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 185-200
 Mechanical Behavior and Structure of Advanced Fe-Cr-Al Alloy Weldments  (M. N. Gussev, K. G. Field, E. Cakmak, Y. Yamamoto)....Pages 201-214
 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 215-234
 Steam Oxidation Behavior of FeCrAl Cladding  (B. A. Pint, K. A. Terrani, R. B. Rebak)....Pages 235-244
 In-Situ Proton Irradiation-Corrosion Study of ATF Candidate Alloys in Simulated PWR Primary Water  (Peng Wang, Gary S. Was)....Pages 245-258
 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 259-267
 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 269-280
 Corrosion of Multilayer Ceramic-Coated ZIRLO Exposed to High Temperature Water  (Kiran K. Mandapaka, Gary S. Was)....Pages 281-292
Front Matter ....Pages 293-293
 Calibration of the Local IGSCC Engineering Model for Alloy 600  (Thierry Couvant, Jacqueline Caballero, Cécilie Duhamel, Jérôme Crépin, Takaharu Maeguchi)....Pages 295-317
 Prediction of IGSCC as a Finite Element Modeling Post-analysis  (Thierry Couvant)....Pages 319-334
 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 335-345
 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 347-355
 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 357-372
 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 373-387
Front Matter ....Pages 389-389
 SCC and Fracture Toughness of XM-19  (Peter Andresen, Martin Morra, Robert Carter)....Pages 391-406
 On the Effect of Preoxidation of Nickel Alloy X-750  (Silvia Tuzi, Kenneth Göransson, Fang Liu, Mattias Thuvander, Krystyna Stiller)....Pages 407-416
 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 417-431
 Effect of Chloride Transients on Crack Growth Rates in Low Alloy Steels in BWR Environments  (Xiaoyuan Lou, Raj Pathania)....Pages 433-445
 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 447-456
 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 457-467
 SCC Mitigation in Boiling Water Reactors: Platinum Deposition and Durability on Structural Materials  (Pascal V. Grundler, Stefan Ritter, Lyubomira Veleva)....Pages 469-484
 Confirmation of On-Line NobleChem™ (OLNC) Mitigation Effectiveness in Operating Boiling Water Reactors (BWRs)  (Joe Kopcash, Juan Varela, Hubert Huie, G. Depta)....Pages 485-496
 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 497-507
 In Situ Electrochemical Study on Crevice Environment of Stainless Steel in High Temperature Water  (Y. Soma, C. Kato, F. Ueno)....Pages 509-521
Front Matter ....Pages 523-523
 Corrosion Fatigue Crack Initiation in Zr-2.5Nb  (H. M. Nordin, A. J. Phillion, T. M. Karlsen, S. Persaud)....Pages 525-541
 Cluster Dynamics Model for the Hydride Precipitation Kinetics in Zirconium Cladding  (Donghua Xu, Hang Xiao)....Pages 543-552
 Modeling Corrosion Kinetics of Zirconium Alloys in Loss-of-Coolant Accident (LOCA)  (Léo Borrel, Adrien Couet)....Pages 553-563
 Progressing Zirconium-Alloy Corrosion Models Using Synchrotron XANES  (Michael Moorehead, Adrien Couet, Jing Hu, Zhonghou Cai)....Pages 565-576
 Advanced Characterization of Hydrides in Zirconium Alloys  (S. M. Hanlon, S. Y. Persaud, F. Long, M. R. Daymond)....Pages 577-597
 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 599-610
Front Matter ....Pages 611-611
 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 613-624
 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 625-641
 Microstructural Evolution of Cast Austenitic Stainless Steels Under Accelerated Thermal Aging  (Timothy G. Lach, Thak Sang Byun)....Pages 643-652
 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 653-661
 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 663-672
 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 673-687
 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 689-702
 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 703-710
Front Matter ....Pages 711-711
 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 713-732
 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 733-747
 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 749-762
 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 763-777
 A Statistical Analysis on Modeling Uncertainty Through Crack Initiation Tests  (Jae Phil Park, Chanseok Park, Chi Bum Bahn)....Pages 779-795
Front Matter ....Pages 797-797
 Laboratory Analysis of a Leaking Letdown Cooler from Oconee Unit 3  (James Hyres, Rocky Thompson, Jim Batton)....Pages 799-818
 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 819-829
 Microbially Induced Corrosion in Firefighting Systems—Experience and Remedies  (Ulla Ehrnstén, Leena Carpén, Kimmo Tompuri)....Pages 831-840
 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 841-852
 Identification of PWR Stainless Steel Piping Safety Significant Locations Susceptible to Stress Corrosion Cracking  (R. Hosler, A. Kulp, P. Stevenson, S. Petro)....Pages 853-878
Front Matter ....Pages 879-879
 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 881-897
 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 899-918
 Hydrogen Trapping by Irradiation-Induced Defects in 316L Stainless Steel  (Anne-Cécile Bach, Frantz Martin, Cécilie Duhamel, Stéphane Perrin, François Jomard, Jérôme Crépin)....Pages 919-935
 Grain Boundary Oxidation of Neutron Irradiated Stainless Steels in Simulated PWR Water  (Takuya Fukumura, Koji Fukuya, Katsuhiko Fujii, Terumitsu Miura, Yuji Kitsunai)....Pages 937-947
 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 949-960
 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 961-972
 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 973-991
Front Matter ....Pages 993-993
 Irradiation-Assisted Stress Corrosion Cracking Initiation Screening Criteria for Stainless Steels in PWR Systems  (Steve Fyfitch, Sarah Davidsaver, Kyle Amberge)....Pages 995-1004
 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 1005-1013
 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 1015-1026
 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 1027-1037
 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 1039-1054
 Effect of Specimen Size on the Crack Growth Rate Behavior of Irradiated Type 304 Stainless Steel  (A. Jenssen, P. Chou, C. Tobpasi)....Pages 1055-1072
 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 1073-1084
Front Matter ....Pages 1085-1085
 Effect of Grain Orientation on Irradiation Assisted Corrosion of 316L Stainless Steel in Simulated PWR Primary Water  (Rigel D. Hanbury, Gary S. Was)....Pages 1087-1096
 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 1097-1109
 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 1111-1126
Front Matter ....Pages 1127-1127
 Effect of Applied Potential and Inhibitors on PbSCC of Alloy 690TT  (Brent Capell, Jesse Lumsden, Michael Calabrese, Rick Eaker)....Pages 1129-1144
 Corrosion of SG Tube Alloys in Typical Secondary Side Local Chemistries Derived from Operating Experience  (Ian de Curieres)....Pages 1145-1163
 Investigation on the Effect of Lead (Pb) on the Degradation Behavior of Passive Films on Alloy 800  (J. Ulaganathan, H. Ha)....Pages 1165-1181
 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 1183-1192
 Stress Corrosion Cracking of Alloy 800 in Secondary Side Crevice Environment  (Maria-Lynn Komar, Guylaine Goszczynski)....Pages 1193-1203
 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 1205-1235
Back Matter ....Pages 1237-1308