Radiation effects on polymers for coatings on copper canisters used for the containment of radioactive materials
Source abstract
Abstract
Abstract The present work proposes applying polyurethane coatings as an additional barrier in the design of Canadian nuclear waste disposal containers. The goal of the present research is to investigate the physico-mechanical integrity of a natural castor oil-based polyurethane (COPU) to be used as a coating material in pH–radiation–temperature environments. As the first part to these inquiries, the present paper investigates the effect of a mixed radiation field supplied by a SLOWPOKE-2 nuclear research reactor on COPUs that differ only by their isocyanate structure. FTIR, DSC, DMA, WAXS, and MALDI are used to characterize the changes that occur as a result of radiation and to relate these changes to polymer structure and composition. The COPUs used in the present work have demonstrated sustained physico-mechanical properties up to accumulated doses of 2.0 MGy and are therefore suitable for end-uses in radiation environments such as those expected in the deep geological repository.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Building materials and conservation · Concrete and Cement Materials Research · Infrastructure Maintenance and Monitoring
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (21)
Show source-provided references
1. Atomic Energy Limited of Canada, Environmental Impact Statement on the Concept for disposal of Canada’s Nuclear fuel waste, AECL-10711, COG-93-1, 1994.
2. H.W. Bonin, I. Miedema, V.T. Bui, in: Proceedings of the 23rd Annual Conference of the Canadian Nuclear Society, 2002.
3. I. Miedema, Application of advanced polymeric composites to spent nuclear fuel disposal containers, MSc. Thesis, Royal Military College of Canada, 2002.
4. Nuclear Waste Management Organization, Choosing a way forward. The Future Management of Canada’s Used Nuclear Fuel. Final Study, 2005.
5. CTECH Radioactive Materials Management, Conceptual Design for a Deep Geological Repository for Used Nuclear Fuel, Annex 1, Metallurgical Aspects of Used Fuel Design, 2002.
6. Shoesmith · Mat. Res. Soc. Symp. Proc. · 1996 · 412 · 56310.1557/PROC-412-563 ↗
7. M. Walker, Polymeric Radioactive Waste Disposal Containers. An investigation into the application of polymers to house low and intermediate level radioactive waste, MSc. Thesis, Royal Military College of Canada, 2001.
8. O. Davey, T. Douglas, C. Duriez, B. MacGregor, Examination of the feasibility of using polymeric composites in the fabrication of a container for the long-term disposal of spent nuclear fuel, RMC-CEE-CME417-97-2, 1997.
9. C.A. McKenna, K.R. Hoffman, M.R. Dunning, Epoxy composite Container vessels for the long-term storage of spent nuclear fuel: Heat transfer effects and limitations, RMC-CCE_CM417-99-3, 1999.
10. Brown · J. Nucl. Mater. · 2005 · 341 · 11510.1016/j.jnucmat.2005.01.012 ↗
11. A. Mortley, Radiation effects on the properties of a polyurethane/epoxy graft interpenetrating polymer network. An investigation into the application of polymers in the fabrication of containers to store radioactive waste, MSc. Thesis, Royal Military College of Canada, 2005.
12. Liu · J. Appl. Polym. Sci. · 1995 · 56 · 350
13. Kumar · Indian J. Technol. · 1983 · 21 · 517
14. Kendaganna Swamy · J. Mater. Sci. · 2003 · 38 · 453
15. Liu · J. Appl. Polym. Sci. · 1995 · 56 · 350
16. Petrovic · J. Appl. Polym. Sci. · 1984 · 29 · 103110.1002/app.1984.070290401 ↗
17. An American Standard Test Method, Standard Test Method for Tensile Properties of Plastics, ASTM D638-96, 1996.
18. G.B. Lamarre, Experimental and Computational Determination of Radiation Dose Rates in the SLOWPOKE-2 Research Reactor at the Royal Military College of Canada, MSc. Thesis, Royal Military College of Canada, 1999.
19. Mortley · Nucl. Instrum. and Meth. B · 2007 · 265 · 9810.1016/j.nimb.2007.08.032 ↗
20. McCrum · 1967
21. Schatzki · J. Polym. Sci. · 1962 · 57 · 49610.1002/pol.1962.1205716526 ↗