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

C. Padovani; F.  King; C.  Lilja; D. Feron; 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; Dirk Engelberg; J. J.  Noël; D. W.  Shoesmith

doi:10.1080/1478422X.2017.1356973

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

C. Padovani, F. King, C. Lilja, D. Feron, 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, Dirk Engelberg, J. J. Noël, D. W. Shoesmith

Research output: Contribution to journal › Article › peer-review

Abstract

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.

Original language	English
Journal	Corrosion Engineering Science and Technology
Volume	52
Issue number	S1
Early online date	23 Aug 2017
DOIs	https://doi.org/10.1080/1478422X.2017.1356973
Publication status	Published - 2017

Keywords

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

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1080/1478422X.2017.1356973Licence: CC BY-NC-ND

MPC: Materials Performance Centre
Burke, G. (PI), Engelberg, D. (PI), Preuss, M. (PI), Frankel, P. (PI), Jimenez-Melero, E. (PI), Pickering, E. (PI), Scenini, F. (PI), Stevens, N. (PI), Race, C. (PI), Connolly, B. (PI), Abdallah, M. (PGR student), Armson, S. (PGR student), Attar, H. (PGR student), Barron, P. (PGR student), Bird, J. (PGR student), Brown, A. (PGR student), Bruce, K. (PGR student), Buxton, O. (PGR student), Cassineri, S. (PGR student), Cattivelli, A. (PGR student), Chen, W. (PGR student), Collins, J. (PGR student), Debenham, L. (PGR student), Eaton-Mckay, J. (PGR student), Eguchi, K. (PGR student), Foster, D. (PGR student), Fox, C. (PGR student), Garrett, A. (PGR student), Gredis, A. (PGR student), Grime, T. (PGR student), Hou, J. (PGR student), Howe, B. (PGR student), Hughes, J. (PGR student), Hunt, C. (PGR student), Islam, U. (PGR student), Jalil, R. (PGR student), Jones, C. (PGR student), Kablan, A. (PGR student), Kapousidou, M. (PGR student), Koc, O. (PGR student), Kroll, R. (PGR student), Lang, R. (PGR student), Lennard, J. (PGR student), Liubercev, S. (PGR student), Mahmood, S. (PGR student), Maric, M. (PGR student), Martin, C. (PGR student), Mazzei, G. (PGR student), Rigby-Bell, M. (PGR student), Rogers, M. (PGR student), Sanchez, C. (PGR student), Shah, Z. (PGR student), Stavroulakis, E. (PGR student), Stuglik, P. (PGR student), Suleman, T. (PGR student), Supornpaibul, N. (PGR student), Thornley, S. (PGR student), Volpe, L. (PGR student), Wang, H. (PGR student), Wilson, M. (PGR student), Wilson, A. (PGR student), Woodward, T. (PGR student), Wylie, A. (PGR student), Xu, X. D. (PGR student), Yankova, M. (PGR student), Yildirim, E. (PGR student), Zhou, Y. (PGR student), Zhu, S. (PGR student), Barzdajn, B. (CoI), Carruthers, A. (CoI), Cassineri, S. (CoI), Chang, L. (CoI), Obasi, G. (CoI), Palko, S. (CoI), Reccagni, P. (CoI), Tang, R. (CoI), Thomas, R. (CoI), Unnikrishnan, R. (CoI), Zhang, Z. (CoI), Zhou, Y. (CoI) & Aspinall, A. (Support team)
1/01/02 → …
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Cite this

Padovani, C., King, F., Lilja, C., Feron, D., Necib, S., Crusset, D., Deydier, V., Diomidis, N., Gaggiano, R., Ahn, T., Keech, P. G., Macdonald, D. D., Asano, H., Smart, N., Hall, D. S., Hänninen, H., Engelberg, D., Noël, J. J., & Shoesmith, D. W. (2017). 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. Corrosion Engineering Science and Technology, 52(S1). https://doi.org/10.1080/1478422X.2017.1356973

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title = "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",

abstract = "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.",

keywords = "Nuclear waste management, corrosion , deep geological repository , used fuel container, radioactive waste management, spent fuel container ",

author = "C. Padovani and F. King and C. Lilja and D. Feron and S. Necib and D. Crusset and V. Deydier and N. Diomidis and R. Gaggiano and T Ahn and Keech, {P. G.} and Macdonald, {D. D.} and H. Asano and N Smart and Hall, {D. S.} and H. H{\"a}nninen and Dirk Engelberg and No{\"e}l, {J. J.} and Shoesmith, {D. W.}",

year = "2017",

doi = "10.1080/1478422X.2017.1356973",

language = "English",

volume = "52",

journal = "Corrosion Engineering Science and Technology",

issn = "1478-4221",

publisher = "Sage Publications Ltd",

number = "S1",

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Padovani, C, King, F, Lilja, C, Feron, D, Necib, S, Crusset, D, Deydier, V, Diomidis, N, Gaggiano, R, Ahn, T, Keech, PG, Macdonald, DD, Asano, H, Smart, N, Hall, DS, Hänninen, H, Engelberg, D, Noël, JJ & Shoesmith, DW 2017, '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', Corrosion Engineering Science and Technology, vol. 52, no. S1. https://doi.org/10.1080/1478422X.2017.1356973

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. / Padovani, C.; King, F. ; Lilja, C. et al.
In: Corrosion Engineering Science and Technology, Vol. 52, No. S1, 2017.

Research output: Contribution to journal › Article › peer-review

TY - JOUR

T1 - 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

AU - Padovani, C.

AU - King, F.

AU - Lilja, C.

AU - Feron, D.

AU - Necib, S.

AU - Crusset, D.

AU - Deydier, V.

AU - Diomidis, N.

AU - Gaggiano, R.

AU - Ahn, T

AU - Keech, P. G.

AU - Macdonald, D. D.

AU - Asano, H.

AU - Smart, N

AU - Hall, D. S.

AU - Hänninen, H.

AU - Engelberg, Dirk

AU - Noël, J. J.

AU - Shoesmith, D. W.

PY - 2017

Y1 - 2017

N2 - 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.

AB - 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.

KW - Nuclear waste management

KW - corrosion

KW - deep geological repository

KW - used fuel container

KW - radioactive waste management

KW - spent fuel container

U2 - 10.1080/1478422X.2017.1356973

DO - 10.1080/1478422X.2017.1356973

M3 - Article

SN - 1478-4221

VL - 52

JO - Corrosion Engineering Science and Technology

JF - Corrosion Engineering Science and Technology

IS - S1

ER -

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

Abstract

Keywords

UN SDGs

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MPC: Materials Performance Centre

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