1. 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
- Author
-
D.W. Shoesmith, Dirk Engelberg, Digby D. Macdonald, Nikitas Diomidis, N.R. Smart, James J. Noël, Cristiano Padovani, Didier Crusset, H. Asano, Peter G. Keech, D. Féron, Valérie Deydier, T. Ahn, Christina Lilja, Fraser King, H. Hänninen, Sophia Necib, Roberto Gaggiano, David S. Hall, 551 Harwell, SAPHOS, Nanaimo, BC, Canada, Swedish Nuclear Fuel and Waste Management Co (SKB), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA), ANDRA, National Cooperative for the Disposal of Radioactive Waste (Nagra), ONDRAF, United States Nuclear Regulatory Commission (U.S.NRC), Department of Nuclear Engineering [Berkeley], University of California [Berkeley], University of California-University of California, Radioactive Waste Management RWM, Integrity Corrosion Consulting, Swedish Nuclear Fuel and Waste Management Company SKB, French Alternative Energies and Atomic Energy Commission, National Agency for Radioactive Waste Management ANDRA, National Cooperative for the Disposal of Radioactive Waste NAGRA, National Agency for Radioactive Waste and Enriched Fissile Material ONDRAF/NIRAS, United States Nuclear Regulatory Commission, Nuclear Waste Management Organisation, University of California Berkeley, Radioactive Waste Management Funding and Research Center RWMC, AMEC Foster Wheeler, Department of Mechanical Engineering, University of Manchester, University of Western Ontario, Aalto-yliopisto, Aalto University, University of California [Berkeley] (UC Berkeley), and University of California (UC)-University of California (UC)
- Subjects
[PHYS.NUCL]Physics [physics]/Nuclear Theory [nucl-th] ,used fuel container ,GeneralLiterature_INTRODUCTORYANDSURVEY ,020209 energy ,General Chemical Engineering ,ComputerApplications_COMPUTERSINOTHERSYSTEMS ,02 engineering and technology ,[PHYS.NEXP]Physics [physics]/Nuclear Experiment [nucl-ex] ,12. Responsible consumption ,Corrosion ,High-level waste ,0202 electrical engineering, electronic engineering, information engineering ,Forensic engineering ,General Materials Science ,ta216 ,corrosion ,Waste management ,radioactive waste management ,General Chemistry ,021001 nanoscience & nanotechnology ,Spent nuclear fuel ,13. Climate action ,Container (abstract data type) ,Deep geological repository ,Environmental science ,deep geological repository ,Nuclear waste management ,0210 nano-technology ,spent fuel container - 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. This paper is part of a supplement on the 6th International Workshop on Long-Term Prediction of Corrosion Damage in Nuclear Waste Systems.
- Published
- 2017
- Full Text
- View/download PDF