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

  • John H. Jackson
  • Denise Paraventi
  • Michael Wright
Conference proceedings

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

Table of contents

  1. Front Matter
    Pages i-xxxvii
  2. PWR Nickel SCC—SCC

    1. Front Matter
      Pages 1-1
    2. Warren Bamford, Steve Fyfitch, Raj Pathania, Paul Crooker
      Pages 15-25
    3. Peter L. Andresen, Martin M. Morra, Kawaljit Ahluwalia
      Pages 27-53
    4. Greg Oberson, Margaret Audrain, Jay Collins, Eric Reichelt
      Pages 55-65
    5. B. Alexandreanu, Y. Chen, W. -Y. Chen, K. Natesan
      Pages 67-85
    6. David S. Morton, John V. Mullen, Eric Plesko, John Sutliff, Robert Morris, Nathan Lewis
      Pages 87-103
    7. Takumi Terachi, Takuyo Yamada, Nobuo Totsuka, Koji Arioka
      Pages 105-118
  3. PWR Nickel SCC—Initiation

    1. Front Matter
      Pages 119-119
    2. Peter Andresen, Peter Chou
      Pages 121-135
    3. Mychailo Toloczko, Ziqing Zhai, Stephen Bruemmer
      Pages 137-160
    4. J. Bolivar, T.T. Nguyen, Y. Shi, M. Fregonese, J. Réthoré, J. Adrien et al.
      Pages 161-174
    5. E. Chaumun, J. Crépin, C. Duhamel, C. Guerre, E. Héripré, M. Sennour et al.
      Pages 175-189
    6. Daniel Brimbal, Gary Poling, Darren Wood, Antoine Marion, Nicolas Huin, Olivier Calonne
      Pages 191-201
    7. S. R. Pemberton, M. A. Chatterton, A. S. Griffiths, S. L. Medway, D. R. Tice, K. J. Mottershead
      Pages 203-216
    8. Ziqing Zhai, Mychailo Toloczko, Stephen Bruemmer
      Pages 217-229
  4. PWR Nickel SCC—Aging Effects

    1. Front Matter
      Pages 231-231
    2. B. Stephan, D. Jacob, F. Delabrouille, L. Legras
      Pages 233-249
    3. Fei Teng, Li-Jen Yu, Octav Ciuca, Emmanuelle Marquis, Grace Burke, Julie D. Tucker
      Pages 251-259
    4. Seung Chang Yoo, Kyoung Joon Choi, Seunghyun Kim, Ji-Soo Kim, Byoung Ho Choi, Yun-Jae Kim et al.
      Pages 281-292
    5. Roman Mouginot, Teemu Sarikka, Mikko Heikkilä, Mykola Ivanchenko, Unto Tapper, Ulla Ehrnstén et al.
      Pages 321-334
  5. PWR Nickel SCC—Alloy 600 Mechanistic

    1. Front Matter
      Pages 335-335
    2. Josiane Nguejio, Jérôme Crépin, Cécilie Duhamel, Fabrice Gaslain, Catherine Guerre, François Jomard et al.
      Pages 337-357
    3. Daniel K. Schreiber, Matthew J. Olszta, Karen Kruska, Stephen M. Bruemmer
      Pages 359-374
    4. S. Y. Persaud, B. Langelier, A. Eskandari, H. Zhu, G. A. Botton, R. C. Newman
      Pages 375-398
    5. L. Volpe, G. Bertali, M. Curioni, M. G. Burke, F. Scenini
      Pages 409-422
  6. PWR Nickel SCC—Alloy 690 Mechanistic

    1. Front Matter
      Pages 455-455
    2. Ziqing Zhai, Mychailo Toloczko, Karen Kruska, Daniel Schreiber, Stephen Bruemmer
      Pages 457-483
    3. Takaharu Maeguchi, Kimihisa Sakima, Kenji Sato, Koji Fujimoto, Yasuto Nagoshi, Kazuya Tsutsumi
      Pages 485-500
    4. Tae-Young Ahn, Sung-Woo Kim, Seong Sik Hwang, Hong-Pyo Kim
      Pages 501-507
  7. Irradiation Damage—Stainless Steel

    1. Front Matter
      Pages 547-547
    2. Anna Hojna, Jan Duchon, Patricie Halodova, Hygreeva Kiran Namburi
      Pages 549-563
    3. H. T. Vo, A. Reinhardt, D. Frazer, N. Bailey, P. Chou, P. Hosemann
      Pages 593-603
    4. Takahiro Ishizaki, Yusaku Maruno, Kiyohiro Yabuuchi, Sosuke Kondo, Akihiko Kimura
      Pages 605-615
    5. Siddhartha Pathak, Jordan S. Weaver, Cheng Sun, Yongqiang Wang, Surya R. Kalidindi, Nathan A. Mara
      Pages 617-635
  8. Irradiation Damage—Swelling

About these proceedings


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

Editors and affiliations

  • John H. Jackson
    • 1
  • Denise Paraventi
    • 2
  • Michael Wright
    • 3
  1. 1.Idaho National LaboratoryIdaho FallsUSA
  2. 2.Naval Nuclear LaboratoryPittsburghUSA
  3. 3.Chalk River LaboratoriesCanadian Nuclear LaboratoriesChalk RiverCanada

Bibliographic information

  • DOI
  • Copyright Information The Minerals, Metals & Materials Society 2019
  • Publisher Name Springer, Cham
  • eBook Packages Chemistry and Materials Science
  • Print ISBN 978-3-030-04638-5
  • Online ISBN 978-3-030-04639-2
  • Series Print ISSN 2367-1181
  • Series Online ISSN 2367-1696
  • Buy this book on publisher's site