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

  • Conference proceedings
  • © 2016

Overview

Editors:
  1. Jeremy T. Busby

    1. Oak Ridge National Laboratory, USA

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  2. Gabriel Ilevbare

    1. Electric Power Research Institute, USA

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  3. Peter L. Andresen

    1. GE Global Research Center, USA

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Part of the book series: The Minerals, Metals & Materials Series (MMMS)

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Table of contents (147 papers)

  1. Front Matter

    Pages i-xxx
    Download chapter PDF

  2. Opening Session

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

      • C. E. Gene Carpenter Jr., Amy Hull, Greg Oberson
      Pages 1-12

    2. Conditions for Long Term Operation of Nuclear Power Plants in Sweden

      • Peter Ekström, Karen Gott, Björn Brickstad
      Pages 13-24

  3. Alloy 690 and Its Weld Metals I

    1. Current NRC Perspectives Concerning Primary Water Stress Corrosion Cracking

      • David Alley, Darrell Dunn
      Pages 25-39

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

      • Kazuya Tsutsumi, Thierry Couvant
      Pages 41-53

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

      • Koji Arioka, Tomoki Miyamoto, Takuyo Yamada, Takumi Terachi
      Pages 55-69

    4. Crack growth testing on Cold Worked Alloy 690 in Primary Water Environment

      • David R. Tice, Stuart L. Medway, Norman Platts, John W. Stairmand
      Pages 71-89

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

      • Mychailo B. Toloczko, Matthew J. Olszta, Stephen M. Bruemmer
      Pages 91-107

  4. Alloy 690 and Its Weld Metals II

    1. Cyclic and SCC Behavior of Alloy 690 HAZ in a PWR Environment

      • Bogdan Alexandreanu, Yiren Chen, Ken Natesan, Bill Shack
      Pages 109-129

    2. Stress Corrosion Crack Growth Rate Testing of Novel Composite Arrest Specimens

      • David S. Morton, John V. Mullen, Eric Plesko, John Sutliff, Nathan Lewis
      Pages 131-147

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

      • Qunjia Peng, Tetsuo Shoji, Juan Hou, Yoichi Takeda, Toshio Yonezawa
      Pages 149-159

    4. SCC of Alloy 690 and its Weld Metals

      • Peter L. Andresen, Martin M. Morra, Kawaljit Ahluwalia
      Pages 161-178

    5. SCC Behavior of Alloy 152 Weld in a PWR Environment

      • Bogdan Alexandreanu, Yiren Chen, Ken Natesan, Bill Shack
      Pages 179-196

  5. Alloy 690 and Its Weld Metals III

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

      • Hannu Hänninen, Aki Toivonen, Anssi Brederholm, Tapio Saukkonen, Wade Karlsen, Ulla Ehrnsten et al.
      Pages 197-224

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

      • M. B. Toloczko, M. J. Olszta, S. M. Bruemmer
      Pages 225-243

    3. Cyclic and SCC Behavior of Alloy 52M/182 Weld Overlay in a PWR Environment

      • Bogdan Alexandreanu, Yiren Chen, Ken Natesan, Bill Shack
      Pages 245-266

    4. SCC of High CR Alloys in BWR Environments

      • Peter L. Andresen
      Pages 267-300

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

      • S. M. Bruemmer, M. J. Olszta, M. B. Toloczko, L. E. Thomas
      Pages 301-314

  6. Alloy 690 and Its Weld Metals IV

    1. Research and Evaluation of Low Temperature Crack Propagation of Ni Base Alloys in Actual Plants

      • Kimihisa Sakima, Harutaka Suzuki, Hideki Fujiwara
      Pages 315-329

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

      • Matthew J. Olszta, Daniel K. Schreiber, Larry E. Thomas, Stephen M. Bruemmer
      Pages 331-342
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Keywords

About this book

This 15th Edition of the International Conference on Materials Degradation in Light Water Reactors focuses on subject areas critical to the safe and efficient running of nuclear reactor systems through the exchange and discussion of reseach results as well as field operating and management experience.

Editors and Affiliations

  • Oak Ridge National Laboratory, USA

    Jeremy T. Busby

  • Electric Power Research Institute, USA

    Gabriel Ilevbare

  • GE Global Research Center, USA

    Peter L. Andresen

About the editors

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. For more information on TMS, visit www.tms.org.

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