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Overview of NRC Proactive Management of Materials Degradation (PMMD) Program

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Conditions for Long Term Operation of Nuclear Power Plants in Sweden

Current NRC Perspectives Concerning Primary Water Stress Corrosion Cracking

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Evaluation of the Susceptibility to SCC Initiation of Alloy 690 in Simulated PWR Primary Water

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Role of Cavity Formation on Crack Growth of Cold‐Worked Carbon Steel, TT 690 and MA 600 in High Temperature Water

Crack Growth Testing on Cold Worked Alloy 690 in Primary Water Environment

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One Dimensional Cold Rolling Effects on Stress Corrosion Crack Growth in Alloy 690 Tubing and Plate Materials

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Cyclic and SCC Behavior of Alloy 690 HAZ in a PWR Environment<link></link><link></link>

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Stress Corrosion Crack Growth Rate Testing of Novel Composite Arrest Specimens

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Environmentally Assisted Crack Growth in Cold Worked Alloy 690TT in Primary Water at Low and High Temperatures

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SCC of Alloy 690 and its Weld Metals

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SCC Behavior of Alloy 152 Weld in a PWR Environment<link></link><link></link>

Effect of Hot Cracks on EAC Crack Initiation and Growth in Nickel‐Base Alloy Weld Metals

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Stress Corrosion Crack Growth of Alloy 52M in Simulated PWR Primary Water

Cyclic and SCC Behavior of Alloy 52M/182 Weld Overlay in a PWR Environment<link></link><link></link>

SCC of High CR Alloys in BWR Environments

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High‐Resolution Characterizations of Grain Boundary Damage and Stress Corrosion Cracks in Cold‐Rolled Alloy 690

Research and Evaluation of Low Temperature Crack Propagation of NI Base Alloys in Actual Plants

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Penetrative Internal Oxidation from Alloy 690 Surfaces and Stress Corrosion Crack Walls during Exposure to PWR Primary Water

Predicting Chromium Depletion of Nickel Base Alloys

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In‐situ and Ex‐situ Oxide Characterization by Synchrotron X‐ray (SPring‐8) in Non‐Sensitized 316 Stainless Steel and High Temperature Water Combination

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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

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Oxide Film Characterization along Crack Paths in Stainless Steel in Aerated and Deaerated Water Environments

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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

Questions & Answers

The Effect of Cold Work on Microstructure and SCC Susceptibility in Simulated BWR Environment for Non‐Sensitized Austenitic Stainless Steels

Behavior of Stress Corrosion Cracking for type 316L Stainless Steel with Controlled Distribution of Surface Work Hardened Layer in Simulated Boiling Water Reactors Environment

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Influence of Bulk and Surface Cold Work on Crack Initiation and Crack Growth of Austenitic Stainless Steels under Simulated BWR Environment

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Effect of Nitrogen Addition in 304L Stainless Steel on the IGSCC Crack Growth Rate in Simulated BWR Environment

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Characterization of Type 304L Stainless Steel: Comparison of ASTM A262 Practice a and Analytical Electron Microscopy Techniques

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The Effect of Grain Size on IGSCC in SS 316L in Simulated BWR Environment

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An Investigation into Stress Corrosion Cracking of Dissimilar Metal Welds with 304L Stainless Steel and Alloy 82 in High Temperature Pure Water

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Deformation Mode and Microstructure on Stress Corrosion Cracking Path and Kinetics in High Temperature Water Environments

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Effect of Static Load Hold Periods on the Corrosion Fatigue Behavior of Austenitic Stainless Steels in Simulated BWR Environments

Effects of Material Composition on Corrosion Fatigue Crack Growth of Austenitic Stainless Steels in High Temperature Water

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Fatigue Limit and Hysteresis Behavior of Type 304L Stainless Steel in Air and PWR Water, at 150°C and 300°C

NRC Research Activities on Environmentally‐Assisted Fatigue

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PWR Fuel Deposit Analysis at a B&W Plant with a 24 Month Fuel Cycle

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Effect of DH Concentration on Crud Deposition on Heated Zircaloy‐4 in Simulated PWR Primary Water

Questions & Answers

Use of the Areva BWR Crud Model to Study High Zinc Operation at a US Plant

Electrochemical Study of Pre ‐ and Post‐Transition Corrosion of Zr Alloys in PWR Coolant

Areva Fuel Condition Index for a Pressurized Water Reactor

Structure and Thermodynamical Properties of Zirconium Hydrides from First‐Principle

Questions & Answers

Hydride Behavior in Zircaloy‐4 during Thermomechanical Cycling

Development of a Method for Studying the Influence of Stress State on the Iodine‐Induced Stress Corrosion Cracking of Zirconium Alloys

Wear of Zircaloy‐4 Grid Straps Due to Fretting and Periodic Impacting with RV Internals Baffle Plates

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Microstructure and SCC of Alloy X‐750

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Stress Corrosion Cracking and Crack Tip Characterization of Alloy X‐750 in Boiling Water Reactor Environments

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SCC Properties of Modified Alloy 718 in BWR Plant

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Influence of Chloride Ions as Contaminants on the Corrosion Behavior of Alloy 718 in Pool Water of Nuclear Power Plants

Stress Corrosion Cracking Behavior near the Fusion Boundary of Dissimilar Weld Joint with Alloy 182‐A533B Low Alloy Steel

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Effect of Chloride on Environmentally Assisted Cracking of Low Alloy Steels in Oxygenated High‐Temperature Water ‐ General Corrosion

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The Effect of Temperature on the Crack Growth Rate of Stainless Steel and NI‐Alloys in Simulated BWR Environment

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Effects of Temperature and Corrosion Potential on SCC

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Effect of Thermal Aging on SCC, Material Properties and Fracture Toughness of Stainless Steel Weld Metals

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Flow Accelerated Corrosion of Carbon Steel in the Feedwater System of PWR Plants ‐ Behaviour of Welds and Weld Assemblies

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Modelling Material Effects in Flow‐Accelerated Corrosion

3D Atom‐Probe Characterization of Stress and Cold‐Work in Stress Corrosion Cracking of 304 Stainless Steel

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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

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Influence of Primary Water Chemistry on Oxides Formed on Alloy 600 and Alloy 690