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

1. Front Matter

   Pages i-xxxvii

   PDF

2. PWR Nickel SCC—SCC

   1. Front Matter

      Pages 1-1

      PDF

   2. Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and Variant Weld Material

      • Amanda R. Jenks, Glenn A. White, Paul Crooker

      Pages 3-14

   3. Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components

      • Warren Bamford, Steve Fyfitch, Raj Pathania, Paul Crooker

      Pages 15-25

   4. SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water

      • Peter L. Andresen, Martin M. Morra, Kawaljit Ahluwalia

      Pages 27-53

   5. NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys

      • Greg Oberson, Margaret Audrain, Jay Collins, Eric Reichelt

      Pages 55-65

   6. Stress Corrosion Cracking of Alloy 52/152 Weldments Near Dissimilar Metal Weld Interfaces

      • B. Alexandreanu, Y. Chen, W. -Y. Chen, K. Natesan

      Pages 67-85

   7. Stress Corrosion Crack Growth Rate Testing of Composite Material Specimens

      • David S. Morton, John V. Mullen, Eric Plesko, John Sutliff, Robert Morris, Nathan Lewis

      Pages 87-103

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

      • Takumi Terachi, Takuyo Yamada, Nobuo Totsuka, Koji Arioka

      Pages 105-118

3. PWR Nickel SCC—Initiation

   1. Front Matter

      Pages 119-119

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   2. Crack Initiation of Alloy 600 in PWR Water

      • Peter Andresen, Peter Chou

      Pages 121-135

   3. SCC Initiation Behavior of Alloy 182 in PWR Primary Water

      • Mychailo Toloczko, Ziqing Zhai, Stephen Bruemmer

      Pages 137-160

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

      • J. Bolivar, T.T. Nguyen, Y. Shi, M. Fregonese, J. Réthoré, J. Adrien et al.

      Pages 161-174

   5. Stress Corrosion Cracking Initiation of Alloy 82 in Hydrogenated Steam

      • E. Chaumun, J. Crépin, C. Duhamel, C. Guerre, E. Héripré, M. Sennour et al.

      Pages 175-189

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

      • Daniel Brimbal, Gary Poling, Darren Wood, Antoine Marion, Nicolas Huin, Olivier Calonne

      Pages 191-201

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

      • S. R. Pemberton, M. A. Chatterton, A. S. Griffiths, S. L. Medway, D. R. Tice, K. J. Mottershead

      Pages 203-216

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

      • Ziqing Zhai, Mychailo Toloczko, Stephen Bruemmer

      Pages 217-229

4. PWR Nickel SCC—Aging Effects

   1. Front Matter

      Pages 231-231

      PDF

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

      • B. Stephan, D. Jacob, F. Delabrouille, L. Legras

      Pages 233-249

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

      • Fei Teng, Li-Jen Yu, Octav Ciuca, Emmanuelle Marquis, Grace Burke, Julie D. Tucker

      Pages 251-259

This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.

• Materials degradation
• Environmental degradation
• Water reactors
• Nuclear power systems
• Corrosion

• Idaho National Laboratory, Idaho Falls, USA

  John H. Jackson

• Naval Nuclear Laboratory, Pittsburgh, USA

  Denise Paraventi

• Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, Canada

  Michael Wright

The Minerals, Metals & Materials Society (TMS) is a member-driven international professional society dedicated to fostering the exchange of learning and ideas across the entire range of materials science and engineering, from minerals processing and primary metals production, to basic research and the advanced applications of materials. Included among its nearly 13,000 professional and student members are metallurgical and materials engineers, scientists, researchers, educators, and administrators from more than 70 countries on six continents.

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