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

Stress Corrosion Crack Growth Rate Testing of Composite Material Specimens

Pages 87-103

Morton, David S. (et al.)

Investigation of Hydrogen Behavior in Relation to the PWSCC Mechanism in Alloy TT690

Pages 105-118

Terachi, Takumi (et al.)

Crack Initiation of Alloy 600 in PWR Water

Pages 121-135

Andresen, Peter (et al.)

SCC Initiation Behavior of Alloy 182 in PWR Primary Water

Pages 137-160

Toloczko, Mychailo (et al.)

Multiple Cracks Interactions in Stress Corrosion Cracking: In Situ Observation by Digital Image Correlation and Phase Field Modeling

Pages 161-174

Bolivar, J. (et al.)

Stress Corrosion Cracking Initiation of Alloy 82 in Hydrogenated Steam

Pages 175-189

Chaumun, E. (et al.)

Application of Ultra-High Pressure Cavitation Peening on Reactor Vessel Head Penetration, BMN and Primary Nozzles

Pages 191-201

Brimbal, Daniel (et al.)

The Effect of Surface Condition on Primary Water Stress Corrosion Cracking Initiation of Alloy 600

Pages 203-216

Pemberton, S. R. (et al.)

Microstructural Effects on SCC Initiation in PWR Primary Water for Cold-Worked Alloy 600

Pages 217-229

Zhai, Ziqing (et al.)

A Kinetic Study of Order-Disorder Transition in Ni–Cr Based Alloys

Pages 233-249

Stephan, B. (et al.)

The Role of Stoichiometry on Ordering Phase Transformations in Ni–Cr Alloys for Nuclear Applications

Pages 251-259

Teng, Fei (et al.)

The Effect of Hardening via Long Range Order on the SCC and LTCP Susceptibility of a Nickel-30Chromium Binary Alloy

Pages 261-279

Moss, Tyler E. (et al.)

PWSCC Initiation of Alloy 600: Effect of Long-Term Thermal Aging and Triaxial Stress

Pages 281-292

Yoo, Seung Chang (et al.)

Stress Corrosion Cracking Behavior of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water

Pages 293-305

Wang, Mi (et al.)

Time- and Fluence-to-fracture Studies of Alloy 718 in Reactor

Pages 307-320

Joseph Long, C.

Development of Short-Range Order and Intergranular Carbide Precipitation in Alloy 690 TT upon Thermal Ageing

Pages 321-334

Mouginot, Roman (et al.)

Diffusion Processes as Possible Mechanisms for Cr Depletion at SCC Crack Tip

Pages 337-357

Nguejio, Josiane (et al.)

Role of Grain Boundary Cr5B3 Precipitates on Intergranular Attack in Alloy 600

Pages 359-374

Schreiber, Daniel K. (et al.)

Advanced Characterization of Oxidation Processes and Grain Boundary Migration in Ni Alloys Exposed to 480 °C Hydrogenated Steam

Pages 375-398

Persaud, S. Y. (et al.)

Exploring Nanoscale Precursor Reactions in Alloy 600 in H2/N2–H2O Vapor Using In Situ Analytical Transmission Electron Microscopy

Pages 399-407

Burke, M. G. (et al.)

Electrochemical and Microstructural Characterization of Alloy 600 in Low Pressure H2-Steam

Pages 409-422

Volpe, L. (et al.)

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

Pages 423-437

Stjärnsäter, Johan (et al.)

A Mechanistic Study of the Effect of Temperature on Crack Propagation in Alloy 600 Under PWR Primary Water Conditions

Pages 439-454

Shen, Zhao (et al.)

Grain Boundary Damage Evolution and SCC Initiation of Cold-Worked Alloy 690 in Simulated PWR Primary Water

Pages 457-483

Zhai, Ziqing (et al.)

PWSCC Susceptibility of Alloy 690, 52 and 152

Pages 485-500

Maeguchi, Takaharu (et al.)

Relationship Among Dislocation Density, Local Strain Distribution, and PWSCC Susceptibility of Alloy 690

Pages 501-507

Ahn, Tae-Young (et al.)

Morphology Evolution of Grain Boundary Carbides Precipitated Near Triple Junctions in Highly Twinned Alloy 690

Pages 509-517

Li, Hui (et al.)

A Mechanistic Study of Stress Corrosion Crack Propagation in Heavily Cold Worked TT Alloy 690 Exposed to Simulated PWR Primary Water

Pages 519-534

Yonezawa, Toshio (et al.)

Microstructural Study on the Stress Corrosion Cracking of Alloy 690 in Simulated Pressurized Water Reactor Primary Environment

Pages 535-545

Kuang, Wenjun (et al.)

Effect of Strain Rate and High Temperature Water on Deformation Structure of VVER Neutron Irradiated Core Internals Steel

Pages 549-563

Hojna, Anna (et al.)

Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts

Pages 565-580

Michalička, Jan (et al.)

In Situ and Ex Situ Observations of the Influence of Twin Boundaries on Heavy Ion Irradiation Damage Effects in 316L Austenitic Stainless Steels

Pages 581-591

Bellefon, G. Meric (et al.)

In Situ Microtensile Testing for Ion Beam Irradiated Materials

Pages 593-603

Vo, H. T. (et al.)

Development of High Irradiation Resistant and Corrosion Resistant Oxide Dispersion Strengthened Austenitic Stainless Steels

Pages 605-615

Ishizaki, Takahiro (et al.)

Spherical Nanoindentation Stress-Strain Analysis of Ion-Irradiated Tungsten

Pages 617-635

Pathak, Siddhartha (et al.)

Formation of He Bubbles by Repair-Welding in Neutron-Irradiated Stainless Steels Containing Surface Cold-Worked Layer

Pages 639-650

Koshiishi, Masato (et al.)

Predictions and Measurements of Helium and Hydrogen in PWR Structural Components Following Neutron Irradiation and Subsequent Charged Particle Bombardment

Pages 651-668

Garner, F. A. (et al.)

Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation

Pages 669-680

Sun, C. (et al.)

Carbon Contamination, Its Consequences and Its Mitigation in Ion-Simulation of Neutron-Induced Swelling of Structural Metals

Pages 681-693

Shao, Lin (et al.)

Void Swelling Screening Criteria for Stainless Steels in PWR Systems

Pages 695-708

Davidsaver, Sarah (et al.)

Theoretical Study of Swelling of Structural Materials in Light Water Reactors at High Fluencies

Pages 709-723

Golubov, S. I. (et al.)

High Resolution Transmission Electron Microscopy of Irradiation Damage in Inconel X-750

Pages 727-741

Judge, C. D. (et al.)

In Situ SEM Push-to-Pull Micro-tensile Testing of Ex-service Inconel X-750

Pages 743-757

Howard, C. (et al.)

Microstructural Characterization of Proton-Irradiated 316 Stainless Steels by Transmission Electron Microscopy and Atom Probe Tomography

Pages 759-772

Lim, Yun Soo (et al.)

Microstructural Effects on Stress Corrosion Initiation in Austenitic Stainless Steel in PWR Environments

Pages 775-792

Tice, D. R. (et al.)

Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water

Pages 793-810

Scenini, F. (et al.)

SCC Initiation in the Machined Austenitic Stainless Steel 316L in Simulated PWR Primary Water

Pages 811-827

Chang, Litao (et al.)

High-Resolution Characterisation of Austenitic Stainless Steel in PWR Environments: Effect of Strain and Surface Finish on Crack Initiation and Propagation

Pages 829-847

Pimentel, G. (et al.)

SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions

Pages 849-863

Huin, Nicolas (et al.)

SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions

Pages 865-880

Herbst, Matthias (et al.)

The Effect of Microchemistry on the Crack Response of Lightly Cold Worked Dual Certified Type 304/304L Stainless Steel After Sensitizing Heat Treatment

Pages 881-891

Fisher, K. B. (et al.)

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

Pages 895-911

Paraventi, D. J. (et al.)

Electrical Potential Drop Observations of Fatigue Crack Closure

Pages 913-925

West, E. A.

The Effect of Environment and Material Chemistry on Single-Effects Creep Testing of Austenitic Stainless Steels

Pages 927-942

O’Brien, L. B. (et al.)

Corrosion Fatigue Behavior of Austenitic Stainless Steel in a Pure D2O Environment

Pages 943-956

Yu, L. (et al.)

Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments

Pages 957-986

Medway, S. L. (et al.)

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

Pages 987-1006

Herbst, M. (et al.)

Evaluation of Additively Manufactured Materials for Nuclear Plant Components

Pages 1009-1020

Horn, R. M. (et al.)

Hot Cell Tensile Testing of Neutron Irradiated Additively Manufactured Type 316L Stainless Steel

Pages 1021-1038

Freyer, Paula D. (et al.)

Computational and Experimental Studies on Novel Materials for Fission Gas Capture

Pages 1039-1050

Zhang, Shenli (et al.)

Hydrogen Assisted Cracking Studies of a 12% Chromium Martensitic Stainless Steel—Influence of Hardness, Stress and Environment

Pages 1051-1065

Horner, D. A. (et al.)

Investigation of Flow Accelerated Corrosion Models to Predict the Corrosion Behavior of Coated Carbon Steels in Secondary Piping Systems

Pages 1067-1076

Kim, Seunghyun (et al.)

Effect of High-Temperature Water Environment on the Fracture Behaviour of Low-Alloy RPV Steels

Pages 1077-1099

Que, Z. (et al.)

Corrosion Fatigue Testing of Low Alloy Steel in Water Environment with Low Levels of Oxygen and Varied Load Dwell Times

Pages 1101-1108

Gabris, Cybele

Feasibility Study of the Internal Zr/ZrO2 Reference Electrodes in Supercritical Water Environments

Pages 1109-1122

Li, Yu-Hsuan (et al.)

Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation

Pages 1125-1140

Merezhko, D. A. (et al.)

Quantifying Erosion-Corrosion Impacts on Light Water Reactor Piping

Pages 1141-1156

Guzmán-Leong, C. E. (et al.)

Effect of Molybdate Anion Addition on Repassivation of Corroding Crevice in Austenitic Stainless Steel

Pages 1157-1168

Watanabe, Shun (et al.)

Effect of pH on Hydrogen Pick-Up and Corrosion in Zircaloy-4

Pages 1169-1180

Sayers, James (et al.)

Oxidation Kinetics of Austenitic Stainless Steels as SCWR Fuel Cladding Candidate Materials in Supercritical Water

Pages 1181-1194

Abe, Hiroshi (et al.)

A Recent Look at CANDU Feeder Cracking: High Resolution Transmission Electron Microscopy and Electron Energy Loss Near Edge Structure (ELNES)

Pages 1195-1215

Judge, C. D. (et al.)

Simultaneous Thermal and Gamma Radiation Aging of Electrical Cable Polymers

Pages 1219-1226

Fifield, Leonard S.

Principal Component Analysis (PCA) as a Statistical Tool for Identifying Key Indicators of Nuclear Power Plant Cable Insulation Degradation

Pages 1227-1239

Silva, Chamila C. (et al.)

How Can Material Characterization Support Cable Aging Management?

Pages 1241-1256

Rouison, David (et al.)

Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants

Pages 1257-1265

Duckworth, R. C. (et al.)

Frequency Domain Reflectometry Modeling and Measurement for Nondestructive Evaluation of Nuclear Power Plant Cables

Pages 1267-1280

Glass, S. W. (et al.)

Aging Mechanisms and Nondestructive Aging Indicator of Filled Cross-Linked Polyethylene (XLPE) Exposed to Simultaneous Thermal and Gamma Radiation

Pages 1281-1291

Liu, Shuaishuai (et al.)

Successful Detection of Insulation Degradation in Cables by Frequency Domain Reflectometry

Pages 1293-1301

Ohki, Yoshimichi (et al.)

Capacitive Nondestructive Evaluation of Aged Cross-Linked Polyethylene (XLPE) Cable Insulation Material

Pages 1303-1313

Shao, Z. H. (et al.)

Tracking of Nuclear Cable Insulation Polymer Structural Changes Using the Gel Fraction and Uptake Factor Method

Pages 1315-1321

Correa, Miguel (et al.)

Degradation of Silicone Rubber Analyzed by Instrumental Analyses and Dielectric Spectroscopy

Pages 1323-1332

Ohki, Yoshimichi (et al.)

Automated Detection of Alkali-Silica Reaction in Concrete Using Linear Array Ultrasound Data

Pages 1335-1345

Clayton, Dwight A. (et al.)

Coupled Physics Simulation of Expansive Reactions in Concrete with the Grizzly Code

Pages 1347-1357

Spencer, Benjamin W. (et al.)

Overview of EPRI Long Term Operations Work on Nuclear Power Plant Concrete Structures

Pages 1359-1365

Wall, Joe (et al.)

The Effects of Neutron Irradiation on the Mechanical Properties of Mineral Analogues of Concrete Aggregates

Pages 1367-1377

Rosseel, Thomas M. (et al.)

Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization

Pages 1381-1389

Field, Kevin G. (et al.)

Interdiffusion Behavior of FeCrAl with U3Si2

Pages 1391-1400

Hoggan, Rita E. (et al.)

Mechanical Behavior of FeCrAl and Other Alloys Following Exposure to LOCA Conditions Plus Quenching

Pages 1401-1416

Dolley, Evan J. (et al.)

Mechanical Behavior and Structure of Advanced Fe-Cr-Al Alloy Weldments

Pages 1417-1430

Gussev, M. N. (et al.)

Investigating Potential Accident Tolerant Fuel Cladding Materials and Coatings

Pages 1431-1450

Daub, K. (et al.)

Steam Oxidation Behavior of FeCrAl Cladding

Pages 1451-1460

Pint, B. A. (et al.)

In-Situ Proton Irradiation-Corrosion Study of ATF Candidate Alloys in Simulated PWR Primary Water

Pages 1461-1474

Wang, Peng (et al.)

Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings

Pages 1475-1483

Raiman, Stephen S. (et al.)

Characterization of the Hydrothermal Corrosion Behavior of Ceramics for Accident Tolerant Fuel Cladding

Pages 1485-1496

Doyle, Peter J. (et al.)

Corrosion of Multilayer Ceramic-Coated ZIRLO Exposed to High Temperature Water

Pages 1497-1508

Mandapaka, Kiran K. (et al.)

Calibration of the Local IGSCC Engineering Model for Alloy 600

Pages 1511-1533

Couvant, Thierry (et al.)

Prediction of IGSCC as a Finite Element Modeling Post-analysis

Pages 1535-1550

Couvant, Thierry

Monte Carlo Simulation Based on SCC Test Results in Hydrogenated Steam Environment for Alloy 600

Pages 1551-1561

Sakakibara, Yohei (et al.)

Protection of the Steel Used for Dry Cask Storage System from Atmospheric Corrosion by Tio2 Coating

Pages 1563-1571

Yang, Jing-Ru (et al.)

Predictive Modeling of Baffle-Former Bolt Failures in Pressurized Water Reactors

Pages 1573-1588

Banyay, Gregory A. (et al.)

Technical Basis and SCC Growth Rate Data to Develop an SCC Disposition Curve for Alloy 82 in BWR Environments

Pages 1589-1603

Kumagai, Katsuhiko (et al.)

SCC and Fracture Toughness of XM-19

Pages 1607-1622

Andresen, Peter (et al.)

On the Effect of Preoxidation of Nickel Alloy X-750

Pages 1623-1632

Tuzi, Silvia (et al.)

Microstructures of Oxide Films Formed in Alloy 182 BWR Core Shroud Support Leg Cracks

Pages 1633-1647

Chen, Jiaxin (et al.)

Effect of Chloride Transients on Crack Growth Rates in Low Alloy Steels in BWR Environments

Pages 1649-1661

Lou, Xiaoyuan (et al.)

Electrochemical Behavior of Platinum Treated Type 304 Stainless Steels in Simulated BWR Environments Under Startup Conditions

Pages 1663-1672

Yuan, Chu-Yung (et al.)

Investigations of the Dual Benefits of Zinc Injection on Cobalt-60 Uptake and Oxide Film Formation Under Boiling Water Reactor Conditions

Pages 1673-1683

Holdsworth, Samuel (et al.)

SCC Mitigation in Boiling Water Reactors: Platinum Deposition and Durability on Structural Materials

Pages 1685-1700

Grundler, Pascal V. (et al.)

Confirmation of On-Line NobleChem™ (OLNC) Mitigation Effectiveness in Operating Boiling Water Reactors (BWRs)

Pages 1701-1712

Kopcash, Joe (et al.)

Development of the Fundamental Multiphysics Analysis Model for Crevice Corrosion Using a Finite Element Method

Pages 1713-1723

Tachibana, Masahiko (et al.)

In Situ Electrochemical Study on Crevice Environment of Stainless Steel in High Temperature Water

Pages 1725-1737

Soma, Y. (et al.)

Corrosion Fatigue Crack Initiation in Zr-2.5Nb

Pages 1741-1757

Nordin, H. M. (et al.)

Cluster Dynamics Model for the Hydride Precipitation Kinetics in Zirconium Cladding

Pages 1759-1768

Xu, Donghua (et al.)

Modeling Corrosion Kinetics of Zirconium Alloys in Loss-of-Coolant Accident (LOCA)

Pages 1769-1779

Borrel, Léo (et al.)

Progressing Zirconium-Alloy Corrosion Models Using Synchrotron XANES

Pages 1781-1792

Moorehead, Michael (et al.)

Advanced Characterization of Hydrides in Zirconium Alloys

Pages 1793-1813

Hanlon, S. M. (et al.)

Influence of Alloying Elements and Effect of Stress on Anisotropic Hydrogen Diffusion in Zr-Based Alloys Predicted by Accelerated Kinetic Monte Carlo Simulations

Pages 1815-1826

Yu, Jianguo (et al.)

Influence of δ-Ferrite Content on Thermal Aging Induced Mechanical Property Degradation in Cast Stainless Steels

Pages 1829-1840

Byun, Thak Sang (et al.)

Microstructure and Deformation Behavior of Thermally Aged Cast Austenitic Stainless Steels

Pages 1841-1857

Chen, Y. (et al.)

Microstructural Evolution of Cast Austenitic Stainless Steels Under Accelerated Thermal Aging

Pages 1859-1868

Lach, Timothy G. (et al.)

Electrochemical Characteristics of Delta Ferrite in Thermally Aged Austenitic Stainless Steel Weld

Pages 1869-1877

Subramanian, Gokul Obulan (et al.)

Effect of Long-Term Thermal Aging on SCC Initiation Susceptibility in Low Carbon Austenitic Stainless Steels

Pages 1879-1888

Aoki, So (et al.)

Crack Growth Rate and Fracture Toughness of CF3 Cast Stainless Steels at ~3 DPA

Pages 1889-1903

Chen, Y. (et al.)

Effects of Thermal Aging and Low Dose Neutron Irradiation on the Ferrite Phase in a 308L Weld

Pages 1905-1918

Li, Z. (et al.)

Microstructural Evolution of Welded Stainless Steels on Integrated Effect of Thermal Aging and Low Flux Irradiation

Pages 1919-1926

Bjurman, Martin (et al.)

The Use of Tapered Specimens to Evaluate the SCC Initiation Susceptibility in Alloy 182 in BWR and PWR Environments

Pages 1929-1948

Bai, Juxing (et al.)

Effect of Thermal Aging on Fracture Mechanical Properties and Crack Propagation Behavior of Alloy 52 Narrow-Gap Dissimilar Metal Weld

Pages 1949-1963

Ahonen, Matias (et al.)

Distribution and Characteristics of Oxide Films Formed on Stainless Steel Cladding on Low Alloy Steel in Simulated PWR Primary Water Environments

Pages 1965-1978

Xiong, Qi (et al.)

Microstructural Characterization of Alloy 52 Narrow-Gap Dissimilar Metal Weld After Aging

Pages 1979-1993

Sarikka, Teemu (et al.)

A Statistical Analysis on Modeling Uncertainty Through Crack Initiation Tests

Pages 1995-2011

Park, Jae Phil (et al.)

Laboratory Analysis of a Leaking Letdown Cooler from Oconee Unit 3

Pages 2015-2034

Hyres, James (et al.)

Root Cause Analysis of Cracking in Alloy 182 BWR Core Shroud Support Leg Cracks

Pages 2035-2045

Bjurman, Martin (et al.)

Microbially Induced Corrosion in Firefighting Systems—Experience and Remedies

Pages 2047-2056

Ehrnstén, Ulla (et al.)

Managing the Ageing Degradation of Concealed Safety Relevant Cooling Water Piping in European S/KWU LWRs

Pages 2057-2068

Widera, Martin (et al.)

Identification of PWR Stainless Steel Piping Safety Significant Locations Susceptible to Stress Corrosion Cracking

Pages 2069-2094

Hosler, R. (et al.)

On the Use of Density-Based Algorithms for the Analysis of Solute Clustering in Atom Probe Tomography Data

Pages 2097-2113

Marquis, Emmanuelle A. (et al.)

Comparative Study on Short Time Oxidation of Un-Irradiated and Protons Pre-Irradiated 316L Stainless Steel in Simulated PWR Water

Pages 2115-2134

Boisson, M. (et al.)

Hydrogen Trapping by Irradiation-Induced Defects in 316L Stainless Steel

Pages 2135-2151

Bach, Anne-Cécile (et al.)

Grain Boundary Oxidation of Neutron Irradiated Stainless Steels in Simulated PWR Water

Pages 2153-2163

Fukumura, Takuya (et al.)

Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments—Part I: Microstructure Characterization

Pages 2165-2176

Song, M. (et al.)

Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking

Pages 2177-2188

Wang, Mi (et al.)

Solute Clustering in As-irradiated and Post-irradiation-Annealed 304 Stainless Steel

Pages 2189-2207

Chen, Yimeng (et al.)

Irradiation-Assisted Stress Corrosion Cracking Initiation Screening Criteria for Stainless Steels in PWR Systems

Pages 2211-2220

Fyfitch, Steve (et al.)

Novel Technique for Quantitative Measurement of Localized Stresses Near Dislocation Channel—Grain Boundary Interaction Sites in Irradiated Stainless Steel

Pages 2221-2229

Johnson, D. C. (et al.)

IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation Annealing

Pages 2231-2242

Hesterberg, Justin R. (et al.)

Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 Exposed to BWR Environments

Pages 2243-2253

Teysseyre, S. (et al.)

Evaluation of Crack Growth Rates and Microstructures Near the Crack Tip of Neutron-Irradiated Austenitic Stainless Steels in Simulated BWR Environment

Pages 2255-2270

Chimi, Yasuhiro (et al.)

Effect of Specimen Size on the Crack Growth Rate Behavior of Irradiated Type 304 Stainless Steel

Pages 2271-2288

Jenssen, A. (et al.)

Plastic Deformation Processes Accompanying Stress Corrosion Crack Propagation in Irradiated Austenitic Steels

Pages 2289-2300

Gussev, M. N. (et al.)

Effect of Grain Orientation on Irradiation Assisted Corrosion of 316L Stainless Steel in Simulated PWR Primary Water

Pages 2303-2312

Hanbury, Rigel D. (et al.)

Finite Element Modelling to Investigate the Mechanisms of CRUD Deposition in PWR

Pages 2313-2325

Wu, Jiejie (et al.)

Properties of Oxide Films on Ni–Cr–xFe Alloys in a Simulated PWR Water Environment

Pages 2327-2342

Ru, Xiangkun (et al.)

Effect of Applied Potential and Inhibitors on PbSCC of Alloy 690TT

Pages 2345-2360

Capell, Brent (et al.)

Corrosion of SG Tube Alloys in Typical Secondary Side Local Chemistries Derived from Operating Experience

Pages 2361-2379

Curieres, Ian

Investigation on the Effect of Lead (Pb) on the Degradation Behavior of Passive Films on Alloy 800

Pages 2381-2397

Ulaganathan, J. (et al.)

Influence of Alloying on α-αʹ Phase Separation in Duplex Stainless Steels

Pages 2399-2408

Garfinkel, David A. (et al.)

Stress Corrosion Cracking of Alloy 800 in Secondary Side Crevice Environment

Pages 2409-2419

Komar, Maria-Lynn (et al.)

Using Modern Microscopy to “Fingerprint” Secondary Side SCC in Ni–Fe Alloys

Pages 2421-2451

Persaud, S. Y. (et al.)