The corrosion behaviour of candidate container materials for the disposal of high-level waste and spent fuel–a summary of the state of the art and opportunities for synergies in future R&D

Research output: Contribution to journalArticleScientificpeer-review


  • C. Padovani
  • F. King
  • C. Lilja
  • D. Féron
  • S. Necib
  • D. Crusset
  • V. Deydier
  • N. Diomidis
  • R. Gaggiano
  • T. Ahn
  • P. G. Keech
  • D. D. Macdonald
  • H. Asano
  • N. Smart
  • D. S. Hall
  • H. Hänninen
  • D. Engelberg
  • J. J. Noël
  • D. W. Shoesmith

Research units

  • United States Nuclear Regulatory Commission
  • University of California at Berkeley
  • Radioactive Waste Management Funding and Research Center RWMC
  • University of Manchester
  • Radioactive Waste Management RWM
  • Integrity Corrosion Consulting
  • Swedish Nuclear Fuel and Waste Management Company SKB
  • French Alternative Energies and Atomic Energy Commission CEA
  • National Agency for Radioactive Waste Management ANDRA
  • National Cooperative for the Disposal of Radioactive Waste NAGRA
  • AMEC Foster Wheeler
  • National Agency for Radioactive Waste and enriched Fissile Material ONDRAF/NIRAS
  • Nuclear Waste Management Organization NWMO
  • University of Western Ontario


This paper presents a state-of-the-art analysis of the expected degradation processes of a variety of candidate container materials for the disposal of high-level waste and/or spent nuclear fuel. The work, focusing on the most recent developments, has been performed under the auspices of the Implementing Geological Disposal Technology Platform in the context of an international conference hosted by the Nuclear Waste Management Organisation of Canada (NWMO). The scope of the analysis includes the expected corrosion and environmentally assisted cracking behaviour of copper, carbon steel and titanium in contact with relevant buffer materials (e.g. bentonite, cement) and in conditions expected in an underground disposal facility (long-term anoxic conditions). Considerations relative to the expected evolution of the environmental conditions (especially in the period following backfilling) are also presented. Beyond summarising the current state of knowledge, areas in which opportunities for international collaboration may be present are also highlighted. This paper is part of a supplement on the 6th International Workshop on Long-Term Prediction of Corrosion Damage in Nuclear Waste Systems.


Original languageEnglish
Pages (from-to)227-231
Number of pages5
JournalCorrosion Engineering Science and Technology
Publication statusPublished - 28 Apr 2017
MoE publication typeA1 Journal article-refereed

    Research areas

  • corrosion, deep geological repository, Nuclear waste management, radioactive waste management, spent fuel container, used fuel container

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