Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors

Front Matter....Pages i-xxx
Overview of NRC Proactive Management of Materials Degradation (PMMD) Program....Pages 1-12
Conditions for Long Term Operation of Nuclear Power Plants in Sweden....Pages 13-24
Current NRC Perspectives Concerning Primary Water Stress Corrosion Cracking....Pages 25-39
Evaluation of the Susceptibility to SCC Initiation of Alloy 690 in Simulated PWR Primary Water....Pages 41-53
Role of Cavity Formation on Crack Growth of Cold-Worked Carbon Steel, TT 690 and MA 600 in High Temperature Water....Pages 55-69
Crack growth testing on Cold Worked Alloy 690 in Primary Water Environment....Pages 71-89
One Dimensional Cold Rolling Effects on Stress Corrosion Crack Growth in Alloy 690 Tubing and Plate Materials....Pages 91-107
Cyclic and SCC Behavior of Alloy 690 HAZ in a PWR Environment....Pages 109-129
Stress Corrosion Crack Growth Rate Testing of Novel Composite Arrest Specimens....Pages 131-147
Environmentally Assisted Crack Growth in Cold Worked Alloy 690TT in Primary Water at Low and High Temperatures....Pages 149-159
SCC of Alloy 690 and its Weld Metals....Pages 161-178
SCC Behavior of Alloy 152 Weld in a PWR Environment....Pages 179-196
Effect of Hot Cracks on EAC Crack Initiation and Growth in Nickel-Base Alloy Weld Metals....Pages 197-224
Stress Corrosion Crack Growth of Alloy 52M in Simulated PWR Primary Water....Pages 225-243
Cyclic and SCC Behavior of Alloy 52M/182 Weld Overlay in a PWR Environment....Pages 245-266
SCC of High CR Alloys in BWR Environments....Pages 267-300
High-Resolution Characterizations of Grain Boundary Damage and Stress Corrosion Cracks in Cold-Rolled Alloy 690....Pages 301-314
Research and Evaluation of Low Temperature Crack Propagation of Ni Base Alloys in Actual Plants....Pages 315-329
Penetrative Internal Oxidation from Alloy 690 Surfaces and Stress Corrosion Crack Walls during Exposure to PWR Primary Water....Pages 331-342
Predicting Chromium Depletion of Nickel Base Alloys....Pages 343-356
In-situ and Ex-situ Oxide Characterization by Synchrotron X-ray (SPring-8) in Non-sensitized 316 Stainless Steel and High Temperature Water Combination....Pages 357-370
High Resolution Electron Microscopy Study on Oxide Films Formed on Nickel-Base Alloys X-750, 182 and 82 in Simulated High Flow Velocity BWR Water Conditions....Pages 371-388
Oxide Film Characterization Along Crack Paths in Stainless Steel in Aerated and Deaerated Water Environments....Pages 389-407
Non-Linear Dynamics of the Morphology at the Oxide / Metal Interface of Austenitic Steels in Simulated Light Water Reactor Environments and its Implications for SCC Initiation....Pages 409-424
The Effect of Cold Work on Microstructure and SCC Susceptibility in Simulated BWR Environment for Non-Sensitized Austenitic Stainless Steels....Pages 425-437
Behavior of Stress Corrosion Cracking for Type 316L Stainless Steel With Controlled Distribution of Surface Work Hardened Layer in Simulated Boiling Water Reactors Environment....Pages 439-452
Influence of Bulk and Surface Cold Work on Crack Initiation and Crack Growth of Austenitic Stainless Steels under Simulated BWR Environment....Pages 453-469
Effect of Nitrogen Addition in 304 L Stainless Steel on the IGSCC Crack Growth Rate in Simulated BWR Environment....Pages 471-490
Characterization of Type 304L Stainless Steel: Comparison of ASTM A262 Practice A and Analytical Electron Microscopy Techniques....Pages 491-503
The Effect of Grain Size on IGSCC in SS 316L in Simulated BWR Environment....Pages 505-520
An Investigation into Stress Corrosion Cracking of Dissimilar Metal Welds with 304L Stainless Steel and Alloy 82 in High Temperature Pure Water....Pages 521-532
Deformation Mode and Microstructure on Stress Corrosion Cracking Path and Kinetics in High Temperature Water Environments....Pages 533-545
Effect of Static Load Hold Periods on the Corrosion Fatigue Behavior of Austenitic Stainless Steels in Simulated BWR Environments....Pages 547-560
Effects of Material Composition on Corrosion Fatigue Crack Growth of Austenitic Stainless Steels in High Temperature Water....Pages 561-581
Fatigue limit and Hysteresis Behavior of Type 304L Stainless Steel in Air and PWR Water, at 150°C and 300°C....Pages 583-603
NRC Research Activities on Environmentally-Assisted Fatigue....Pages 605-619
PWR Fuel Deposit Analysis at a B&W Plant with a 24 Month Fuel Cycle....Pages 621-631
Effect of DH Concentration on Crud Deposition on Heated Zircaloy-4 in Simulated PWR Primary Water....Pages 633-648
Use of the AREVA BWR CRUD Model to Study High Zinc Operation at a US Plant....Pages 649-653
Electrochemical study of pre- and post-transition corrosion of Zr alloys in PWR coolant....Pages 655-663
AREVA Fuel Condition Index for a Pressurized Water Reactor....Pages 665-669
Structure and Thermodynamical Properties of Zirconium Hydrides from First-Principle....Pages 671-681
Hydride Behavior in Zircaloy-4 During Thermomechanical Cycling....Pages 683-688
Development of a method for studying the influence of stress state on the iodine-induced stress corrosion cracking of zirconium alloys....Pages 689-701
Wear of Zircaloy-4 Grid Straps Due to Fretting and Periodic Impacting with RV Internals Baffle Plates....Pages 703-718
Microstructure and SCC of Alloy X-750....Pages 719-744
Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Boiling Water Reactor Environments....Pages 745-762
SCC Properties of Modified Alloy 718 in BWR Plant....Pages 763-780
Influence of Chloride Ions as Contaminants on the Corrosion Behavior of Alloy 718 in Pool Water of Nuclear Power Plants....Pages 781-790
Stress Corrosion Cracking Behavior Near the Fusion Boundary of Dissimilar Weld Joint with Alloy 182-A533B Low Alloy Steel....Pages 791-804
Effect of Chloride on Environmentally Assisted Cracking of Low Alloy Steels in Oxygenated High-Temperature Water — General Corrosion....Pages 805-826
The Effect of Temperature on the Crack Growth Rate of Stainless Steel and Ni-Alloys in Simulated BWR Environment....Pages 827-846
Effects of Temperature and Corrosion Potential on SCC....Pages 849-882
Effect of Thermal Aging on SCC, Material Properties and Fracture Toughness of Stainless Steel Weld Metals....Pages 883-905
Flow Accelerated Corrosion of Carbon Steel in the Feedwater System of PWR Plants - Behaviour of Welds and Weld Assemblies....Pages 907-924
Modelling Material Effects in Flow-Accelerated Corrosion....Pages 925-937
3D Atom-Probe Characterization of Stress and Cold-Work in Stress Corrosion Cracking of 304 Stainless Steel....Pages 939-951
Effect of Dissolved Hydrogen, Surface Conditions and Composition on the Electronic Properties of the Oxide Films Formed on Nickel-Base Alloys in PWR Primary Water....Pages 953-966
Influence of Primary Water Chemistry on Oxides Formed on Alloy 600 and Alloy 690....Pages 967-992
Characterizing environmental degradation in PWRs by 3D FIB sequential sectioning....Pages 993-1006
On the Microstructure of Alloy 600 SCC Cracks Observed by TEM on PWR SG Pulled Tubes and on Laboratory Specimens....Pages 1007-1021
Balance of Plant Corrosion Issues in Aging Nuclear Power Plants....Pages 1023-1035
Containment Liner Corrosion....Pages 1037-1049
Electrochemical Studies of Steam Generator Tube Degradation in the Presence of Thiosulphate....Pages 1051-1064
X-Ray Photoelectron Study of the Oxides Formed on Nickel Metal and Nickel-Chromium 20% Alloy Surfaces Under Reducing and Oxidizing Potentials in Basic, Neutral and Acidic Solutions....Pages 1065-1085
Interaction of Microstructure, Composition, and Cold Work on the Stress Corrosion Cracking of Alloy 82 Weld Metal....Pages 1087-1104
Stress Corrosion Cracking Behavior of Dissimilar Metal Weldments in High Temperature Water Environments....Pages 1105-1125
SCC Crack Growth Rate of Alloy 82 in PWR Primary Water Conditions — Effect of a Thermal Treatment....Pages 1127-1139
Initiation of PWSCC of Weld Alloy 182....Pages 1141-1154
NRC/EPRI Welding Residual Stress Validation Program — Phase III....Pages 1155-1168
Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment....Pages 1169-1186
Stress Corrosion Crack Initiation Susceptibility of Irradiated Austenitic Stainless Steels....Pages 1187-1201
Stress Corrosion Cracking Behavior of Type 304 Stainless Steel Irradiated under Different Neutron Dose Rates at JMTR....Pages 1203-1217
In-Pile Tests for IASCC Growth Behavior of Irradiated 316L Stainless Steel under Simulated BWR Condition in JMTR....Pages 1219-1228
Crack Growth Rates of Irradiated Commercial Stainless Steels in BWR and PWR Environments....Pages 1229-1240
The Key Factors Affecting Crack Growth Behavior of Neutron-Irradiated Austenitic Alloys....Pages 1241-1255
Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel WWER Reactor Core Internals....Pages 1257-1275
Slow Strain Rate Tensile Tests of Irradiated Austenitic Stainless Steels in Simulated PWR Environment....Pages 1277-1291
Irradiation assisted stress corrosion cracking of stainless steels in a PWR environment (A combined approach)....Pages 1293-1307
A Preliminary Hybrid Model of Irradiation-Assisted Stress Corrosion Cracking of 300 Series Stainless Steels in PWR Primary Environments....Pages 1309-1327
Oxidation of a Proton-Irradiated 316 Stainless Steel in Simulated BWR NWC Environment....Pages 1329-1338
Irradiation Creep and Irradiation Stress Relaxation of 316 and 304L Stainless Steels in Thermal and Fast Neutron Spectrum Reactors....Pages 1339-1354
Recent Insights on the Parametric Dependence of Irradiation Creep of Austenitic Stainless Steels....Pages 1355-1369
Cluster Dynamics Prediction of the Microstructure Evolution of 300-Series Austenitic Stainless Steel under Irradiation: Influence of Helium....Pages 1371-1382
Role of Slip Behavior in the Irradiation Assisted Stress Corrosion Cracking in Austenitic Steels....Pages 1383-1395
Effect of Environment and Prestrain on IASCC of Austenitic Stainless Steels....Pages 1397-1415
Influence of Localized Plasticity on IASCC Sensitivity of Austenitic Stainless Steels under PWR Primary Water....Pages 1417-1427
Deformation Microstructures of 30 dpa AISI 304 Stainless Steel after Monotonic Tensile and Constant Load Autoclave Testing....Pages 1429-1446
Degradation of Grain Boundary Strength by Oxidation in Alloy 600....Pages 1447-1461
Evaluation of the Oxygen Diffusion Coefficient in Nickel-Base Alloys....Pages 1463-1475
Stress Corrosion Cracking of Alloy 600 in PWR Primary Water : Influence of Chromium, Hydrogen and oxygen Diffusion....Pages 1477-1490
Grain boundary oxidation and embrittlement prior to crack initiation in Alloy 600 in PWR primary water....Pages 1491-1501
Electron Microscopy Characterizations and Atom Probe Tomography of Intergranular Attack in Alloy 600 Exposed to PWR Primary Water....Pages 1503-1517
Grain Boundary Oxidation and Stress Corrosion Cracking in Nickel-Base Alloys Strained in Supercritical Water....Pages 1519-1533
Quantitative Micro-Nano (QMN) Approach to SCC Mechanism and Prediction-Starting a Third Meeting....Pages 1535-1629
Strain Path Effect on IGSCC Initiation and Oxidation of Alloy 182 Exposed to PWR Primary Water....Pages 1631-1646
Experimental Study of Short Crack Coalescence in Nickel-Base Alloys in PWR Primary Water....Pages 1647-1665
Mechanistic Study on PWSCC of Ni Based Alloys Using Hump-SSRT Tests under Dry Hydrogen Gas Environment, Simulated Primary Water and Rapid Straining Electrode Test in Simulated Primary Water....Pages 1667-1684
Crystallographical Characterization of Initiation of Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Environment....Pages 1685-1698
Environmental Effects on PWSCC Initiation and Propagation in Alloy 600....Pages 1699-1713
Probabilistic Environmentally Assisted Cracking Modeling for Primary Water Stress Corrosion Cracking of Alloy 600....Pages 1715-1729
The Role of Lattice Curvature on the SCC Susceptibility of Alloy 600....Pages 1731-1745
PWSCC Susceptibility in Heat Affected Zones of Alloy 600....Pages 1747-1758
Quantitative Residual Strain Analyses on Strain Hardened Nickel Based Alloy....Pages 1759-1771
The Study of Stress Corrosion Cracking on Alloy 600 C-Ring Samples by Polychromatic X-Ray Microdiffraction....Pages 1773-1785
Proposed Coordinated U.S. PWR Reactor Vessel Surveillance Program: An Updated Summary Including Program Optimization....Pages 1787-1799
Developing PWR Aging-Management Strategies for Reactor Vessel Internals....Pages 1801-1810
Development of the Extremely Low Probability of Rupture (xLPR) Code....Pages 1811-1828
Databases of Operationally Induced Damage....Pages 1829-1845
Introduction to a New Real-Time Water Chemistry Measurement System....Pages 1847-1857
Comparison of DBU, NH3, DMA, ETA, and morpholine interactions with ferrous chloride solution and carbon steel surfaces....Pages 1859-1878
Role of Dissolved Hydrogen in Water in Corrosion of Alloy 600 in High Temperature Water....Pages 1879-1892
Quantifying the Benefit of Chemical Mitigation of PWSCC Via Zinc Addition or Hydrogen Optimization....Pages 1893-1908
Computational Thermodynamics for Interpreting Oxidation of Structural Materials in Supercritical Water....Pages 1909-1922
Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water....Pages 1923-1937
Comparison of the Corrosion Behavior of the 14CR ODS Alloy in Steam and Supercritical Water....Pages 1939-1949
Grain Boundary Engineering and Air Oxidation Behavior of Alloy 690....Pages 1951-1965
Developments in SCC Mitigation by Electrocatalysis....Pages 1967-1991
Use of Noble Metal Nanopartice for SCC Mitigation in BWRs....Pages 1993-2003
The Influence of Minor Additions of Platinum Group Metals on Stress Corrosion Cracking in Austenitic Stainless Steels....Pages 2005-2022
The Effect of on-Line Noble Metal Addition on the Shut Down Dose Rates of Boiling Water Reactors....Pages 2023-2037
Effects of Hydrogen on SCC Growth Rate of NI Alloys in BWR Water....Pages 2039-2059
Technical Basis for Water Chemistry Control of IGSCC in Boiling Water Reactors....Pages 2061-2077
Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor During Startup Operations....Pages 2079-2089
Simulation of Water Radiolysis by Sonochemistry: Effects on the Electrochemical Behavior of a Stainless Steel....Pages 2091-2101
Protective Insulated Coating for SCC Mitigation in BWRs....Pages 2103-2119
Influence of Treating Temperature on the Deposition of TIO2 on Type 304 Stainless Steels for Corrosion Mitigation in High Temperature Pure Water....Pages 2121-2136
Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C....Pages 2137-2149
Laboratory Stress Corrosion Cracking Propagation in a Superficial Cold-Worked Layer in SG Divider Plates in Alloy 600....Pages 2151-2170
Destructive Examinations on Divider Plates from Decommissioned Steam Generators Affected by Superficial Stress Corrosion Cracks....Pages 2171-2187
Investigations on Core Basket Bolts from a VVER 440 Power Plant....Pages 2189-2206
Laboratory Analysis of Reactor Coolant Pump Seals....Pages 2207-2218
PWSCC of Thermocoax Pressurizer Heaters in Austenitic Stainless Steel and Remedial Actions to Preventing SCC....Pages 2219-2230
Residual Stress Measurement and the Effect of Heat Treatment in Cladded Control Rod Drive Specimens....Pages 2231-2246
Detailed Root Cause Analysis of SG Tube ODSCC Indications within the Tube Sheets of NPP Biblis Unit A....Pages 2247-2261
Laboratory Investigation of a Leaking Type 316 Socket Weld in a Boron Injection Tank Sampling Line....Pages 2263-2274
Pressure Tests on SG Pulled Tubes at TSP Level....Pages 2275-2286
Implications of Steam Generator Fouling on the Degradation of Material and Thermal Performance....Pages 2287-2301
Key Issues Related to Corrosion Protection of Brackish Water and Seawater Bearing Components in Cooling Water Systems....Pages 2303-2319
Understanding the Limits of Lattice Orientation Data Analysis in Environmental Degradation Studies....Pages 2321-2333
Microstructural Investigation on the Effect of Cold Work on Environmentally Assisted Cracking of Austenitic Stainless Steel....Pages 2335-2350
Plastic strain and residual stress distributions in an AISI 304 stainless steel BWR pipe weld....Pages 2351-2367
Assessment of Lean Grade Duplex Stainless Steels for Nuclear Power Applications....Pages 2369-2380
Effects of Thermo-Mechanical Treatments on Deformation Behavior and IGSCC Susceptibility of Stainless Steels in Pwr Primary Water Chemistry....Pages 2381-2405
SCC Initiation Testing of Alloy 600 in High Temperature Water....Pages 2407-2417
The Effects of Deaerated Water on the Toughness of Nickel-Based Alloys....Pages 2419-2430
Physical Metallurgy, Weldability, and in-Service Performance of Nickel-Chromium Filler Metals Used in Nuclear Power Systems....Pages 2431-2441
Back Matter....Pages 2443-2450