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Preface
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages i-ii
Appendix
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Page iii
Full Issue
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Page 0
Experimental Design to Study the Mechanical Performance of Irradiated Acrylonitrile Butadiene Styrene Fabricated via Fused Filament Fabrication
Arielle J. Miller, Grant Warner, Dharmaraj Raghavan (Howard Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1-10
Irradiation Damage and IASCC of Printed 316L for Use as Fuel Cladding
M. McMurtrey, R. O’Brien, C. Sun, C. Shiau, F. Teng (INL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 11-18
Oxide Dispersion Type 304L Stainlees Steel by Additive Manufacturing Process
Takahiro Ishizaki, Kinya Aota, Yingjuan Yang, Yusaku Maruno, Atsuhiko Onuma (Hitachi)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 19-23
Effect of Follow-Up Post Weld Heat Treatment on Microstructure and PWSCC of Alloy 52M Weld Metal in Dissimilar Metal Weld Joint
Jiarong Ma, Kun Zhang, Tongming Cui, Qi Xiong, Zhanpeng Lu, Junjie Chen (Shanghai Univ), Chendong Yang, Maolong Zhang, Weibao Tang (Shanghai Electric Nuclear Power Group)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 24-34
Characterization of Alloy 52M Weld Metal Near the Fusion Boundary and Oxide Films Formed in Simulated PWR Primary Water
Kun Zhang, Jiarong Ma, Tongming Cui, Zhanpeng Lu, Fei Ning, Yibo Jia, Xue Liang (Shanghai Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 35-45
Effect of Welding Dilution and Dendrite Orientation on SCC Behavior of Alloy 52M Welding Metal in Simulated PWR Primary Water
Jiarong Ma, Kun Zhang, Tongming Cui, Zhanpeng Lu, Xue Liang, Wenqing Liu (Shanghai Univ), Zhiming Zhong, Guangdong Han (State Nuclear Power Plant Service Co.)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 46-55
SCC of Alloy 82 Weld Metal
Peter L. Andresen (Andresen Consulting)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 56-70
Influence of Long-Term Thermal Aging on SCC Initiation Susceptibility of L-Grade Aaustenitic Stainless Steel
K. Kondo, S. Aoki, Y. Fujimura, T. Hirade, Y. Kaji, S. Yamashita (JAEA)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 71-79
Effect of Specimen Size and Percent Engagement on SCC Behavior of Alloy 82 in BWR Environments
Katsuhiko Kumagai, Hiroyuki Nakano, Takayuki Kaminaga (TEPCO)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 80-94
Formulation of the Irradiation Assisted Stress Corrosion Crack Growth Rates for Neutron-Irradiated Stainless Steels in High-Temperature Water of a Boiling Water Reactor
Masato Koshiishi (Nippon Nuclear Fuel Development Co., Ltd.), Kazuhiro Chatani, Shigeaki Tanaka (Toshiba Energy Systems & Solutions Corp.), Hiroyuki Nakano, Takayuki Kaminaga (TEPCO)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 95-102
Effect of Cold Work on Hydrogen Diffusion in Zr-2.5%Nb Alloys at Reactor Temperatures
Heidi Nordin, Jaganathan Ulaganathan, Sean Hanlon, Dylan Broad (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 103-109
Effect of UV Irradiation on Corrosion Behavior of Zirconium Alloy in High Temperature Water Conditions
Taeho Kim, Yalong He, Zefeng Yu, Mohamed S. Elbakhshwan, Li He, Adrien Couet (Univ of Wisconsin, Madison)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 110-114
Development and Validation of a New Experimental Device for Studies of Iodine Stress Corrosion Cracking of Zirconium Alloys
Kamila Wilczynska (CEA/INSA de Lyon), Matthew Bono, David Le Boulch (CEA), Marion Fregonese (INSA de Lyon), Valérie Chabretou (Framatome), Nathanael Mozzani, Laureline Barbie (EDF)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 115-119
Evaluating the Effect of Hydride Embrittlement and Pulse Width on Zircaloy Cladding Transient Performance
D. Kamerman, D. Swank, D. Haggard, A. Matthews, L. Emerson, D. Wachs (INL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 120-126
Low Temperature Crack Propagation Mechanism of Alloy 182 Weld
Young Suk Kim, Sung Soo Kim (KAERI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 127-131
SCC Behavior at Alloy 52M-182 Weld Overlay Interfaces in a PWR Environment
Bogdan Alexandreanu, Yiren Chen (ANL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 132-145
Morphology of Cavities Formed on Grain Boundary of Cracked Alloy TT690
Takumi Terachi, Makie Okamoto, Takuyo Yamada, Koji Arioka (INSS)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 146-155
Effect of Thermal Aging on Microstructure and Hardness of Industrial Heats of Alloy 690
Caitlin Huotilainen, Ulla Ehrnstén, Matias Ahonen (VTT Technical Research Centre of Finland Ltd), Hannu Hänninen (Aalto Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 156-164
Characteristics of Work Hardened Surface Layer on Austenitic Stainless Steels and Its Relation to SCC Susceptibility in High Temperature Water
Hiroshi Abe, Yutaka Watanabe, Takamichi Miyazaki (Tohoku Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 165-173
Next Generation of Noble Metal Application for Boiling Water Reactors
Joe Giannelli, Erica Libra-Sharkey, Collin Custer, George Inch (Nine Mile Point Nuclear Station), Andrew Odell (Exelon Corp.), Michelle Mura (EPRI), Mike Ford (Structural Integrity Assoc)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 174-188
Assessment of the SCC Mitigation Capabilities of the Noble Metal Chemical Application Technology in a Simulated BWR Environment
Pascal V. Grundler, Stefan Ritter, Sriharitha Rowthu, Hans-Peter Seifert (PSI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 189-198
Impact of Corrosion of Nickel Based Coatings for Flow Accelerated Corrosion Control on BWR Radiation Fields
Alfred J. Jarvis, Joseph F. Giannelli, Barry Gordon, David Segletes (Structural Integrity Associates)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 199-206
Revealing How Alkali Cations Affect the Electrical Double Layer Structure of Stainless Steel in Alkaline Aqueous Environments
Rachel Guia P. Giron, Xin Chen, Erika Callagon La Plante (UCLA), Maxim N. Gussev, Keith J. Leonard (ORNL), Gaurav N. Sant (UCLA)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 207-210
Concurrent Effect of Irradiation and Hydrogeneration on Microstructural and Mechanical Properties of Zr Based Fuel Cladding Alloys
Sho Kano, Huilong Yang, John McGrady (Univ of Tokyo), Toru Higuchi, Yoshinori Etoh (Nippon Nuclear Fuel Development Co., Ltd.), Hiroaki Abe (Univ of Tokyo)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 211-218
Characterizing Fatigue Damage in Zr-2.5Nb
H. M. Nordin, M. Mattucci, A. Phillion (CNL), T. M. Karlsen (Inst for Energy Technology)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 219-226
Development of a Gaseous Iodine Testing System to Determine the I-SCC Properties of Zirconium Alloys
Sean M. Hanlon (CNL/Queen’s Univ), Andrew Phillion (CNL), Conor Gillen (Univ of Manchester), Mark R. Daymond (Queen’s Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 227-239
Biaxial Creep of Textured Zr-Nb Alloys
Pratik Joshi, Micah Tillman (NCSU), Nilesh Kumar (Univ of Alabama), Mahmut N. Cinbiz (ORNL), Kurokonda Murty (NCSU)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 240-244
The Mechanistic Understanding on the Stress Corrosion Cracking Growth Rate in Simulated PWR Primary Water for Cold Worked TT Alloy 690
Toshio Yonezawa, Masashi Watanabe (Tohoku Univ), Atsushi Hashimoto (Kobe Material Testing Laboratory Co. Ltd.)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 245-255
Technical Basis for ASME Section XI Code Case for Stress Corrosion Crack Growth Rate Equations for Alloy 690 and Associated Welds
Warren Bamford (Bamford Consulting Services), Amanda Jenks (Dominion Eng), Ron Janowiak (Exelon Corp.), Gary Stevens (EPRI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 256-265
Tests on Mockups Representative of Rolling Zones of Steam Generator Tubes in High Temperature Hydrogenated Water
Daniel Brimbal (Framatome SAS), Steve Fyfitch (Framatome Inc), Olivier Calonne, Nicolas Huin (Framatome SAS)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 266-273
Examination of Cavity Formation in Cold-Worked Alloy 690
Matthew Olszta, Ziqing Zhai, Mychailo Toloczko, Stephen Bruemmer (PNNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 274-285
Non-Destructively Detecting LWR Structural Material Embrittlement Using Transient Grating Spectroscopy
Saleem A. Aldajani, Benjamin R. Dacus, Cody A. Dennett (MIT), M. Grace Burke, Kudzanai Mukahiwa (Manchester Univ), Kuba Anglin (Univ of Santa Cruz), James J. Wall (EPRI), Thak Sang Byun (PNNL), Michael P. Short (MIT)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 286-293
Fracture Property Degradation in Cast Stainless Steels after Long-Term Thermal Aging
T. S. Byun, T. G. Lach, D. A. Collins (PNNL), C. Jang (KAIST)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 294-302
Environmentally Assisted Cracking and Fracture Toughness of an Irradiated Stainless Steel Weld
Y. Chen, B. Alexandreanu (ANL), C. Xu, Y. Yang (Univ of Florida), K. Natesan (ANL), A. S. Rao (NRC)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 303-310
Steam Oxidation, Burst and Critical Heat Flux Testing of Commercial FeCrAl Cladding
B. A. Pint, L. A. Baldesberger, K. A. Kane (ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 311-316
Corrosion Behaviour of Physical Vapour Deposited Coatings on Nuclear Components and Fe-Cr-Al Alloy Under Normal Operation and Accident Scenarios
Caitlin Dever, Mitchell Mattucci (CNL), Kevin Daub, Suraj Persaud (Queen’s Univ), Raul B. Rebak (GE Global Research), Brian Langelier (McMaster Univ), Heidi Nordin (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 317-330
Environmental Degradation Resistance of ATF FeCrAl Cladding Tube Specimens During the Fuel Cycle
Michael Schuster, Evan J. Dolley, Timothy B. Jurewicz,Raul B. Rebak (GE Research)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 331-338
Assessment of Deformation Mechanisms in Neutron-Irradiated Accident-Tolerant FeCrAl Alloys via in Situ Mechanical Testing and TEM Analysis
M. N. Gussev, D. Zhang, K. G. Field (ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 339-345
Mitigation of Primary Water Stress Corrosion Cracking Initiation of Alloy 600
Sonya Pemberton, Jack Beswick, Mark Chatterton, Jill Meadows, Stuart Medway (Woods Nuclear)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 346-355
SCC Initiation of Alloy 82 in Nominal PWR Primary Water at 360°C
Catherine Guerre, Brice Bourdiliau (CEA), Emilien Burger, Thierry Couvant (EdF)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 356-362
SCC Initiation and Growth in PWR Primary Water Containing KOH vs. LiOH
Peter Andresen (Andresen Consulting), Peter Chou (EPRI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 363-372
Crack Initiation Behavior of Cold-Worked Alloy 690 in Simulated PWR Primary Water?Role of Starting Microstructure, Applied Stress and Cold Work on Precursor Damage Evolution
Ziqing Zhai, Matthew Olszta, Mychailo Toloczko, Stephen Bruemmer (PNNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 373-385
Examination of Cracks in Pressure Sensing Lines of the Feed Water System and the Strategy of NPP Goesgen for Replacement
Thomas Wermelinger (NPP Goesgen), Michael Schinhammer (Qualitech AG)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 386-391
Characterization of In Service Thermal Aging Effects in Base Metals and Welds of the Pressure Vessel of a Decommissioned PWR Pressurizer, after 27 Years of Operation
Pierre Joly, Lingtao Sun (Framatome), PåoEfsing (Vattenfall/Ringhals AB), Jean-Paul Massoud (EDF), Frédéric Somville, Robert Gerard (Electrabel), Ying Hui An (CGNPC), Jonathan Bailey (EDF)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 392-400
Stress Corrosion Cracking of A286 Reactor Coolant Pump Turning Vane Bolts
Michael R. Ickes (Westinghouse), Andrew M. Ruminski (NobelClad)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 401-409
Stress Corrosion Cracking of an Austenitic Stainless Steel Pipe Weld
Michael R. Ickes (Westinghouse)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 410-416
Evaluation of the Corrosion Kinetics of SiC with and Without Mitigation Coatings in LWR Chemistries
Peter Doyle (Univ of Tennessee, Knoxville), Stephen Raiman (ORNL), Caen Ang (Univ of Tennessee, Knoxville), Yutai Katoh (ORNL), Steven J. Zinkle (Univ of Tennessee, Knoxville/ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 417-427
Irradiation-Induced Cracking of Dual-Purpose Coatings on SiC
Stephen S. Raiman (ORNL), Peter J. Doyle, Caen Ang (ORNL/Univ of Tennessee), Takaaki Koyanagi (ORNL), David M. Carpenter (MIT), Kurt A. Terrani, Yutai Katoh (ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 428-433
Corrosion of Fe-12Cr-2Si Alloy in High Temperature Steam Environments
Amanda Leong, Jinsuo Zhang, Yi Xie (Virginia Tech)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 434-441
An Investigation into the Corrosion Behaviors of Stainless Steel and Ni-Based Alloy in Simulated PWR Primary Water Environments
Che Jung Chang, Mei Ya Wang, Tsung Kuang Yeh (Natl Tsing Hua Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 442-456
Effect of Local Strain and GND Density on Crack Initiation in Alloy 600
Naganand Saravanan, Phani S. Karamched (Univ of Oxford), Morgane Le Faucheur, Emilien Burger (EDF R&D), Fabio Scenini (Univ of Manchester), Sergio Lozano-Perez (Univ of Oxford)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 457-465
Development of Residual Stress Driven Stress Corrosion Crack Initiation and Growth Specimens
Tyler Moss, John Brockenbrough (NNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 466-475
Corrosion Issues in Future Years: A TSO Overview
Ian de Curieres (IRSN)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 476-484
Operational Experience of Siemens/KWU LWR Nuclear Power Plants
Renate Kilian, Armin Roth (Framatome Gmbh), Marin Widera (RWE Power AG)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 485-493
Design and Fabrication of Alloy A-286 for Resistance to IGSCC in PWRs
Stephen Fyfitch, Sarah Davidsaver (Framatome, Inc.), Kyle Amberge (EPRI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 494-502
Development of Prediction Method for Radiation Hardenening of Reactor Internals
Hitoshi Seto, Yuji Kitsunai (Nippon Nuclear Fuel Development Co., LTD), Shigeaki Tanaka (Toshiba Energy Systems & Solutions Corp.), Ryoji Obata (GE-Hitachi Nuclear)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 503-512
Microstructural Characterization of Proton Irradiated 304L SS at 100°C and 360°C
C. D. Judge (CNL), B. Langelier (McMaster Univ), M. A. Mattucci (CNL), Q. Wang, M. Daymond (Queen’s Univ), G. S. Was (Univ of Michigan), J. Smith (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 513-522
Empirical Equations for Tensile Properties and Stress-Strain Curves of Neutron Irradiated Stainless Steels in LWR Conditions
Koji Fukuya, Katsuhiko Fujii (Inst of Nuclear Safety System), Yasuhiro Chimi, Kuniki Hata (JAEA)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 523-531
Post-Irradiation Examination of High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-Loop Downflow Type PWR
Xiang Chen (ORNL), Tianyi Chen (Oregon State Univ), Chad M. Parish, Mikhail A. Sokolov, Keith J. Leonard (ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 532-538
Effect of Material Condition on Stress Corrosion Crack Initiation of Cold-Worked Alloy 600 in Simulated PWR Primary Water
Ziqing Zhai, Mychailo Toloczko, Stephen M. Bruemmer (PNNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 539-550
The Effect of Diffusion-Induced Grain Boundary Migration Ahead of SCC Crack Tips on Propagation
Zhao Shen (Univ of Oxford), Koji Arioka (Inst of Nuclear Safety Systems), Sergio Lozano-Perez (Univ of Oxford)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 551-562
Understanding the Role of Grain Boundary Migration on the Initiation Stages of PWSCC
L. Volpe, M. G. Burke, F. Scenini (Univ of Manchester)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 563-571
Comparison of Selective Oxidation in Ni-Based Alloys Exposed to PWR Primary Water and Rhines Pack Environments
Karen Kruska, Daniel K. Schreiber, Matthew J. Olszta, Brian J. Riley, Stephen M. Bruemmer (PNNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 572-581
Distinct Effects of Irradiation on the Structure and Chemical Reactivity of Silicates and Carbonates
Erika Callagon La Plante, Yi-Hsuan Hsiao (UCLA), Isabella Pignatelli (Université de Lorraine), Aditya Kumar (Missouri Univ Sci Technol), N.M. Anoop Krishnan (India Inst of Technology), Tandre Oey (UCLA), Howard Dobbs (Univ of California, Santa Barbara), Yingtian Yu (UCLA), Bu Wang (Univ of Wisconsin, Madison), Narayanan Neithalath (Arizona State Univ), Kevin G. Field (ORNL), Jacob Israelachvili (Univ of California, Santa Barbara), Yann Le Pape (ORNL), Mathieu Bauchy, Gaurav Sant (UCLA)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 582-586
Review of Radiation Induced Degradation of Concrete Structure in Commercial Nuclear Power Plants Around Reactor Vessel
Bruce Biwer, David Ma (ANL), Yunping Xi, Yuxiang Jing (Univ of Colorado at Boulder), Madhumita Sircar, Jinsuo Nie (NRC)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 587-601
Effect of Gamma Irradiation on Creep Properties of Cement Paste Analogues
Elena Tajuelo Rodriguez, Yann Le Pape, Thomas M. Rosseel (ORNL), William Hunnicutt (Columbia Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 602-607
Nuclear Concrete Microstructure Generation for Simulating Creep
Christa E. Torrence, Aishwarya Baranikumar, Zachary Grasley (Texas A&M)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 608-614
Radiation-Induced Ferrite Formation as a Potential Issue in PWR Austenitic Internals
D. A. Merezhko, M. S. Merezhko (Institute of Nuclear Physics), O. P. Maksimkin (Inst of Nuclear Physics/Moscow Eng Physics Inst), M. N. Gussev (ORNL), F. A. Garner (Radiation Effects Consulting LLC/Moscow Eng Physics Inst)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 615-624
Investigating the Role of Hydrogen on Stress Corrosion Cracking by Micromechanical Testing
Edward Roberts, Edmund Tarleton (Univ of Oxford), Florence Carrette (EDF R&D), Sergio Lozano-Perez, (Univ of Oxford)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 625-631
In Situ SEM Microtensile Testing of Oxidized grain Boundaries in Alloy 600
E. Still, H. Vo, K. Lam, J. Kabel, R. Auguste (Univ of California, Berkeley), P. Chou (EPRI), P. Hosemann (Univ of California, Berkeley)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 632-636
Transgranular Stress Corrosion Cracking Mechanism of Alloy 690 in Simulated Primary Water
H. P. Kim, S. W. Kim, S. H. Lim, J. Y. Lee, S. H. Cho, M. J. Choi, S. S. Hwang, Y. S. Lim, D. J. Kim (KAERI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 637-644
Effect of Isothermal Aging on Long Range Ordering in Ni-Cr Based Commercial Alloys
Nicholas Aerne, Fei Teng, Julie D. Tucker (Oregon State Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 645-649
3D Creep Response of Nuclear Concrete
Aishwarya Baranikumar, Christa E. Torrence, Zachary Grasley (Texas A&M)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 650-657
Nondestructive Evaluation of Concrete Specimens Representative of Nuclear Power Plants Containing Known Defects
N. Dianne B. Ezell, Austin Albright (ORNL), Dan Floyd (Univ of Tennessee, Knoxville), Lev Khazanovich (Univ of Pittsburgh)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 658-662
Overview of Electric Power Research Institute’s Research on Irradiation of Concrete
Emma L. Wong, James J. Wall (EPRI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 663-667
Alkali-Activated Concretes for Use in Nuclear Facilities and High Temperature Environments
Casey Sundberg, Mary Christiansen, Andrea Schokker, Brian Hinderliter (Univ of Minnesota, Duluth)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 668-675
Microstructure of Ni and X-750 Irradiated at Low and High Temperatures
W. Li, C. Judge, L. Walters (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 676-687
On the Potential Synergies of Helium and Hydrogen on the Nucleation and Stability of Cavity Clusters in Inconel X-750® Irradiated in a High Thermal Neutron Flux Spectra
C. Judge, H. Rajakumar (CNL), A. Korinek (McMaster Univ), Grant Bickel (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 688-694
Modeling the Evolution of Intragranular Helium Bubbles in Nickel Using the Included Phase Model
Andrew A. Prudil, Michael J. Welland, Colin D. Judge (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 695-708
Using a Multi-Scale Approach to Assess the Mechanical Properties and Deformation Mechanisms of High Dose Inconel X-750
C. Howard, C. D. Judge, V. Bhakhri (CNL), Q. Wang, M. R. Daymond (Queen’s Univ), D. Murray, F. Teng (INL), T. Skippon, M. Mattucci, H. Rajakumar, C. Mayhew, C. Dixon, D. Poff, G. A. Bickel (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 709-723
Small Scale Tensile Testing of Grain Boundary Strength of X-750 Alloy
Lingfeng He, Daniel Murray, Xiang Liu, Wen Jiang, Mukesh Bachhav (INL), Xianming Bai (Virginia Tech), Sebastien Teysseyre (INL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 724-727
Oxidation Characteristics of Ni-Cr-Fe Alloy Systems in Simulated PWR Primary Water: Effect of Cr Content
Hee-Sang Shim, Do Haeng Hur (KAERI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 728-734
Effect of Proton-Induced Radiolysis on Corrosion of 316L Stainless Steel in Simulated PWR Primary Water
Rigel D. Hanbury, Gary S. Was (Univ of Michigan)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 735-741
Understanding the Mechanisms of Surface and Crack Tip Oxidation with Valence Mapping
Sergio Lozano-Perez, Zhao Shen (Univ of Oxford), Donghai Du (Shanghai Jiao Tong Univ/Univ of Michigan), Lefu Zhang (Shanghai Jiao Tong Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 742-749
Local Oxidation Penetration of Hydrogen-Charged 308L Stainless Steel Cladding in Deaerated PWR Primary Water
Tongming Cui, Fei Ning, Jiarong Ma, Zhanpeng Lu, Kun Zhang, Yibo Jia, Xue Liang (Shanghai Univ), Xiangkun Ru (Shanghai Univ/Shanghai Electric Nuclear Power Group), Tetsuo Shoji (Tohoku Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 750-764
The Influence of Metal Substrate on CRUD Build-Up Under Simulated PWR Conditions
Stefano Cassineri, Jonathan Duff, Michele Curioni (Univ of Manchester), Andrew Banks (Rolls-Royce plc), Fabio Scenini (Univ of Manchester)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 765-770
Combined Approach to Medium Voltage Cable and Accessories Aging Management Technique at Nuclear Power Plants
Raihan Khondker (STPNOC), Sarajit Banerjee, David Rouison, Rick Easterling (Kinectrics)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 771-779
Cable Aging and CM Approaches Beyond the Shortcomings of IAEA Nuclear Energy Series No. NP-T-3.6
Kenneth T. Gillen (Retired Scientist)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 780-788
“Mind the Gap” Between Old and New Nuclear Qualified Cable: Lessons Learned from Aging, Historical Adverse Events and Other Nuclear Cable Issues
Lawrence Cunningham (CableLAN Nuclear), invited
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 789-803
Nuclear Electrical Penetrator Assemblies and Connectors for Small Modular and Other Advanced Reactors
Pat Kumar (Teledyne Brown Eng), invited
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 804-809
Coupling Effect of Charged-Hydrogen and Cold Work on Oxidation Behavior of 316L Stainless Steel in Deaerated High Temperature Water
Tongming Cui, Jiarong Ma, Fei Ning, Zhanpeng Lu, Kun Zhang, Yibo Jia (Shanghai Univ), Tetsuo Shoji (Tohoku Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 810-823
Characteristics of Oxide Films Formed on 309L and 308L Stainless Steels in Simulated PWR Primary Water
Qi Xiong, Jiarong Ma, Kun Zhang, Tongming Cui, Zhanpeng Lu, Junjie Chen, Yibo Jia (Shanghai Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 824-837
Impact of the Startup Temperature and Primary Chemistry Program on the Oxidation and Release of Corrosion Products from Alloy 690 Steam Generator
Julie Flambard, Florence Carrette, Carole Monchy-Leroy, Martin Bachet, Hadrien Perron (EdF R&D), Lydia Laffont (CIRIMAT)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 838-844
Spatial Resolution of a Cable Fault Location Attempt by Frequency Domain Reflectometry
Yoshimichi Ohki, Naoshi Hirai (Waseda Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 845-851
Inter-Digital Capacitive Sensor for Evaluating Cable Insulation Through Jacket
S. W. Glass, L. S. Fifield (PNNL), A. Sriraman, N. Bowler, (Iowa State Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 852-858
Parameter Sensitivity of Interdigital Sensors for their Design for Cable Insulation Aging Detection
Md. Nazmul Al-Imran (Univ of South Carolina), S. W. Glass, Leonard S. Fifield (PNNL), Mohammod Ali (Univ of South Carolina)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 859-865
Characterizing and Quantifying the Aging of Polyethylene Thin Films Using Novel Doped-Films and Gold Nanoparticle Labeling Strategies Toward Understanding Failure of Cabling Insulation
Daniel Zoltek, Tana O’Keef, Faith Murphy, Magdalene B. Jones (Univ of Minnesota, Duluth), Robert C. Duckworth (ORNL), Brian Hinderliter, Melissa Ann Maurer-Jones (Univ of Minnesota, Duluth)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 866-873
Microstructural Characterization of Steam Generator Tube Flakes from an Operating PWR and Its Galvanic Corrosion Behavior
Soon-Hyeok Jeon, Geun Dong Song, Do Haeng Hur (KAERI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 874-883
Evaluation of the Influence of Irradiation Dose Rate on Crack Growth Behavior of Irradiation Assisted Stress Corrosion Cracking for Neutron-Irradiated Stainless Steels in High-Temperature Water of a Boiling Water Reactor
Masato Koshiishi (Nippon Nuclear Fuel Development Co., Ltd.), Ryoji Obata (Hitachi-GE Nuclear Energy), Hiroyuki Nakano, Takayuki Kaminaga (TEPCO)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 884-891
Electrical Breakdown Strength and AC Withstand in Harvested EPR Insulations for Nuclear Power Plants
Robert Duckworth, Alvin Ellis, Tam Ha (ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 892-898
The Determination of the Reaction Rates, Water Vapor Permeability, and Activation Energies for Thermal Oxidation of LDPE Films
Noumon Munir, Keith B. Lodge, Brian Hinderliter, Melissa A. Maurer-Jones (Univ of Minnesota, Duluth), Robert Duckworth (ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 899-905
Effects of Dry, Wet-Dry Cycling and Aqueous Immersion on Polypropylene and Polyethylene Cable Insulation Mechanical Properties
Isaiah Salinas, Adam Finke, Brian Hinderliter, Keith B. Lodge, Melissa A. Maurer-Jones (Univ of Minnesota, Duluth), Robert Duckworth (ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 906-913
Microstructural Characterization of Reactor Cavity Concrete
J. David Arregui-Mena, Elena Tajuelo Rodriguez, Alain B. Giorla (ORNL), Christa E. Torrence (Texas A&M), Philip D. Edmondson, Yann Le Pape, Thomas M. Rosseel (ORNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 914-916
Development of Mo-Free Low Alloy Steels for Mitigation of Flow Accelerated Corrosion in Secondary Side of PWRs
Seunghyun Kim, Gi Dong Kim (KIMS), Ji Hyun Kim (UNIST)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 917-924
Effects of Aging Temperature and Alloy Composition on Long-Range Ordering in Ni-Cr-Fe Alloys During Isothermal Aging
Xiangkun Ru (Shanghai Electric Nuclear Power Group), Zhanpeng Lu, Jiarong Ma (Shanghai Univ), Chengdong Yang, Qian Yuan, Weibao Tang (Shanghai Electric Nuclear Power Group)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 925-933
Degradation Effects of Hydrogen and High-Temperature Water Environments on the Fracture Resistance of Low-Alloy RPV Steels
Z. Que, H. P. Seifert, P. Spätig, J. Holzer, A. Zhang, G. S. Rao, S. Ritter (PSI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 934-948
Tribocorrosion Phenomena in Co- and Fe-Based Hardfacing Alloys Evaluated Using Pin-on-Disc Wear Tests in a Simulated PWR Environment
V. L. Ratia, M. J. Carrington, D. Zhang, J. L. Daure, D. G. McCartney, P. H. Shipway, (Univ of Nottingham), D. A. Stewart (Rolls Royce plc)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 949-959
Effects of Gamma Ray Irradiation on Corrosion of Carbon Steels at Water Line
Tomomichi Ariga Hiroshi Abe, Yutaka Watanabe (Tohoku Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 960-966
Influence of the Combination of Microstructure and Mechanical Fields on Stress Corrosion Cracking Initiation of Cold-Worked Austenitic Stainless Steels
Qi Huang (PSL Research Univ/Univ Paris), Yann Charles (Univ Paris), Cècilie Duhamel (PSL Research Univ/Univ Paris), Monique Gaspérini (Univ Paris), Jérôme Crépin (PSL Research Univ/Univ Paris)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 967-978
Effect of Martensite on SCC Initiation in Austenitic Stainless Steels in Simulated PWR Primary Water Environment
Litao Chang, M. Grace Burke, Jonathan Duff, Fabio Scenini (Univ of Manchester)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 979-985
Effect of Aerated Transients on Oxidation and SCC of Stainless Steels in PWR Primary Water
Marc Maisonneuve (CEA/PSL Univ), Cécilie Duhamel (PSL Research Univ), Catherine Guerre (CEA), Jérôme Crépin (PSL Research Univ), Ian de Curières (IRSN)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 986-1000
Effect of Strain and Strain Rate on Crack Initiation of 316L Steel in the Simulated PWR Water
Anna Hojná, Mariia Zimina (Centrum výzkumu ?ež), Lukáš Horák (Charles Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1001-1009
The Effect of Irradiation-Induced Matrix Barrier Hardening on Irradiation-Assisted Stress Corrosion Cracking (IASCC) in Austenitic Steels and Nickel Based Alloys
R. G. Faulkner (Loughborough Materials Ltd)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1010-1015
Stress Assessment of Baffle Former Bolt of PWR Reactor for IASCC
A. M. Pandit, F. J. Blom, P. J. Baas (NRG)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1016-1023
Simulating the Susceptibility to IGSCC of Cold Work 316 Austenitic Stainless Steel Exposed to Primary Water
Thierry Couvant, Emilien Burger, Claire Thaury, Claire Rainasse (EdF)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1024-1035
Weibull and Bootstrap Based Probabilistic Fatigue Life Modeling of Stainless Steel Under PWR Coolant Water Environment Condition
Jae Phil Park (Pusan Univ), Subhasish Mohanty (ANL), Chi Bum Bahn (Pusan Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1036-1042
Interface Characterization of Candidate Dual-Purpose Barrier Coatings for SiC/SiC Accident Tolerate Fuel Cladding
Joey Kabel (Univ of California, Berkeley), Takaaki Koyanagi, Yutai Katoh (ORNL), Ryan Schoell, Djamel Kaoumi (NCSU), Caen Ang (Univ of Tennessee, Knoxville), Peter Hosemann (Univ of California, Berkeley/LBNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1043-1051
Corrosion Behavior of Candidate Alloys Used in Supercritical Water Environment
Hsuan-Kan Lin, Tsung-Kuang Yeh, Mei-Ya Wang (Natl Tsing Hua Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1052-1058
Insights into Prospective Fusion Reactor Cooling Systems from Fission Reactor Cooling Circuits
T. L. Martin, A. D. Warren, D. Kumar, A. Siberry, R. Springell (Univ of Bristol), R. Holmes, R. Clark, L. Platts, R. Burrows (NNL), C. Harrington, M. Gorley, E. Surrey (UKAEA), S. Rowthu, P. Grundler, S. Ritter (PSI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1059-1068
High Temperature Cyclic Deformation Behavior of an Advanced Austenitic Stainless Steel (Alloy 709)
Zeinab Y. Alsmadi, Abdullah S. Alomari (NCSU), N. Kumar (Univ of Alabama), K. L. Murty (NCSU)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1069-1075
The Stress Intensity Factor Dependence of 304 Stainless Steel SCC Growth in Deaerated Water
David Morton (NNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1076-1083
Effect of Residual ?-Ferrite on the SCC Behavior of 321 Stainless Steel
Jiamei Wang, Kai Chen, Haozhan Su, Donghai Du, Xianglong Guo, Lefu Zhang, Zhao Shen (Shanghai Jiao Tong Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1084-1094
Stress Corrosion Cracking of Stainless Steel Cladding Layers in Simulated PWR Primary Water
Qi Xiong, Tongming Cui, Jiarong Ma, Zhanpeng Lu, Fei Ning, Junjie Chen, Kun Zhang (Shanghai Univ), Zhiming Zhong, Guangdong Han (State Nuclear Power Plant Service Co.)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1095-1102
Corrosion Performance of Superaustentic Stainless Steel Al-6xn in High Temperature Water
M. J. Stiger (NNL), B. A. Webler (Carnegie Mellon Univ), J. K. Heuer, R. E. Hermer, W. C. Moshier (NNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1103-1114
Understanding the Evolution of Deformation Structures at Fatigue Crack Tips and Implications for Environmentally Enhanced and Retarded Fatigue Crack Growth
B. D. Miller, D. J. Paraventi, B. S. Anglin, T. W. Webb (NNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1115-1128
3D Characterization of Corrosion Fatigue Cracks and Crack Tips Generated in Type 304/304L Stainless Steel During Enhanced and Retarded Fatigue Crack Growth
B. S. Anglin, B. D. Miller, K. B. Fisher, T. W. Webb (NNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1129-1138
Physically-Based Modeling for Environmental Fatigue Crack Growth in Type 304/304L Stainless Steel
B. S. Anglin, J. R. Brockenbrough, J. A. Savchik, C. B. Geller, T. W. Webb (NNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1139-1149
Investigating Pb-Induced Stress Corrosion Cracking of Alloy 800 via In-Situ XPS
B. Payne (CNL), S. Y. Persaud (Queen’s Univ), J. M. Smith (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1150-1159
Stress Corrosion Crack Initiation of Cold-Worked Alloy 800 in Pb-Containing, Alkaline Environments
Jaganathan Ulaganathan, Jared Smith (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1160-1165
Electrochemical Behavior of Dilute Electroactive Species on a Heat-Transfer Surface Under Boiling
Caitlin Dever, Jagan Ulaganathan, Stan Klimas (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1166-1173
Microstructural Characterization of Alloy 690TT Exposed to Pb-Containing Caustic Solutions
G. B. Mazzei, J. Duff, M. G. Burke, F. Scenini (Univ of Manchester), G. Meredith, T. Horner (Rolls-Royce Nuclear)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1174-1180
In-Situ Monitoring of the Corrosion Behavior and Impurity Enrichment of Steam Generator Tube Materials Under PWR Secondary Side Thermal-Hydraulic and Heat Transfer Conditions
Caitlin Huotilainen, Essi Jäppinen, Tiina Ikäläinen, Seppo Peltonen, Timo Saario, Konsta Sipilä (VTT Technical Research Centre of Finland Ltd.)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1181-1190
Environmentally-Assisted Short Crack Fatigue Testing on Austenitic Stainless Steels
B. E. Coult, A. S. Griffiths, J. P. Beswick, P. J. Gill, N. Platts (Wood Plc), J. M. Smith, G. L. Stevens (EPRI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1191-1201
Understanding the Effect of Strain Localization on Corrosion Fatigue of Type 304 Austenitic Stainless Steels in High Temperature Water
Hanxiao Wang, Fabio Scenini, João Quinta da Fonseca, M. Grace Burke (Univ of Manchester), Jill Meadows, Norman Platts, David Tice (Wood plc)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1202-1213
Influence of Mean Stress and Environment on Fatigue Behavior of a 304L SS
Ziling Peng (Pprime Inst/EDF R&D), Gilbert Henaff (Pprime Inst), Jean-Christophe Le Roux, Romain Verlet (EDF R&D)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1214-1222
Stress Corrosion Cracking and Fracture Toughness Tests of an Irradiated Type 304 Stainless Steel
Y. Chen, B. Alexandreanu, K. Natesan (ANL), A. S. Rao (NRC)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1223-1232
IASCC Initiation Test of Neutron Irradiated Type 316L Stainless Steel in Simulated BWR Condition to Evaluate Threshold Stress
Kazuhiro Chatani, Shigeaki Tanaka (Toshiba Energy Systems & Solutions Corp.), Hitoshi Seto (NFD), Hiroyuki Nakano, Takayuki Kaminaga (TEPCO)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1233-1243
Irradiation Assisted Stress Corrosion Cracking (IASCC) of Low Strength and High Strength Alloys in Light Water Reactor Environments
M. Wang (Studsvik Nuclear AB/Univ of Michigan), M. Song (Univ of Michigan), L. Nelson (JLN Consulting), R. Pathania (EPRI), Gary S. Was (Univ of Michigan)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1244-1258
IASCC Susceptibility of Highly Irradiated 316 Stainless Steel in Simulated PWR Primary Water
Donghai Du, Gary S. Was (Univ of Michigan)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1259-1267
Irradiation-Assisted Stress Corrosion Cracking of Ti-Stabilized Austenitic Stainless Steel
Miroslava Ernestova (UJV Rez)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1268-1274
Diffusing Hydrogen Effect on the Oxide Film on 316L SS in High Temperature Water
Jiarong Ma, Tongming Cui, Hao Peng, Zhanpeng Lu, Junjie Chen, Yibo Jia (Shanghai Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1275-1282
Influence of Heat Transfer Crevice Conditions on Stress Corrosion Cracking in Lead Faulted Alkaline Environments
Frederick D. Miller (NNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1283-1294
Use of On-line Monitoring Techniques for Evaluations of Lead Stress Corrosion Cracking (PbSCC) and a PbSCC Inhibitor
Brent Capell (EPRI), Jared Smith (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1295-1303
Hydrogen Assisted Oxidation Behavior of Alloy 600 in High Temperature Air Environment by In-Situ H Charging Method
Zihao Wang, Yoichi Takeda (Tohoku Univ)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1304-1310
Nano-Mechanical Testing of Proton Irradiated 304L SS at 100°C and 360°C to Support IASCC
M. A. Mattucci (CNL), Q. Wang (CNL/Queen’s Univ), T. Skippon (CNL), M. R. Daymond (Queen’s Univ), G. S. Was (Univ of Michigan), J. Smith, C. D. Judge (CNL)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1311-1321
Fracture Behavior of Oxidized Grain Boundary in Neutron-Irradiated Stainless Steel
Terumitsu Miura, Katsuhiko Fujii, Koji Fukuya (Inst of Nuclear Safety System, Inc.), Yuji Kitsunai (Nippon Nuclear Fuel Development Co., Ltd)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1322-1329
Specimen Size Effects on the Crack Growth Rate Response of Highly Irradiated Type 304 Stainless Steel
A. Jenssen, J. Stjärnsäter (Studsvik Nuclear AB), C. Topbasi, P. Chou (EPRI)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1330-1344
Empirical Equations of Crack Growth Rates Based on Data Fitting of Neutron Irradiated Stainless Steel Under High Temperature Water Simulating Boiling Water Reactor Core Conditions
Shigeki Kasahara, Yasuhiro Chimi, Kuniki Hata (JAEA), Koji Fukuya, Katsuhiko Fujii (Inst of Nuclear Safety System. Inc.)
Proceedings | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors | Boston, MA, August 18-22, 2019 | Pages 1345-1355
