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Materials Research in Nuclear Waste Management: Reflections on Twenty-Five MRS Symposia

Published online by Cambridge University Press:  21 March 2011

Rodney C. Ewing
Rodney C. Ewing*
Affiliation:
Department of Nuclear Engineering &Radiological Sciences University of Michigan Ann Arbor, MI 48109-2104, U.S.A.
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Abstract

The MRS symposium, “Scientific Basis for Nuclear Waste Management” was first held in Boston, November 28th to December 1st, 1978. This symposium marks the twenty-fifth in a series that now rotate to meeting sites around the world. During the past 24 years, there has been considerable progress in the development and understanding of the behavior of materials that are used in the processing, transport, containment and disposal of radioactive waste. The design and selection of materials for long-term performance has required a uniquely interdisciplinary effort. Over the same period, there have been important developments in the regulatory framework that guides the scientific and engineering needs of nuclear waste management. This paper provides a subjective commentary on the major developments and innovations during the past 25 symposia. The future challenge will be the proper and constructive integration of the science into the development of nuclear waste disposal strategies.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 713: Symposium JJ – Scientific Basis for Nuclear Waste Management XXV , 2002 , JJ1.1
Copyright
Copyright © Materials Research Society 2002

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References

REFERENCES

1. Bredehoeft, J.D., England, A.W., Steward, D.B., Trask, N.J. and Winograd, I.J., “Geologic Disposal of High-Level Radioactive Wastes – Earth-Science Perspectives,” Geological Survey Circular 779, (1978) 15 pages.Google Scholar
2. Charles, L. “Hebel, Report to the American Physical Society by the Study Group on Nuclear Fuel Cycles and Waste Management,” Reviews in Modern Physics, 50 (1978) 1–12.Google Scholar
3. Committee on Radioactive Waste Management, “Geological Criteria for Repositories for High-Level Radioactive Wastes,” (National Academy of Sciences Press, 1978) 19 pages.Google Scholar
4. Lutze, Werner and Ewing, R.C., Radioactive Waste forms for the Future (Elsevier, 1988) 778 pages.Google Scholar
5. Roy, R., “Science Underlying Radioactive Waste Management: Status and Needs,” Scientific Basis for Nuclear Waste Management, vol. 1, ed. McCarthy, G. J. (Plenum, 1979) pp. 1–20.Google Scholar
6. McCombie, C., “Research Priorities: Are We Tackling the Most Important Problems in Waste Management,” Scientific Basis for Nuclear Waste Management XII, eds. Lutze, W. and Ewing, R.C. (MRS Proceedings, vol. 127, 1989) pp. 3–9.Google Scholar
7. McCombie, C., “R&D in Support of Repository Implementation – Do We Need Any More?”, Scientific Basis for Nuclear Waste Management XXI, eds. McKinley, I.G. and McCombie, C. (MRS Proceedings, vol. 506, 1998) pp. 33–36.Google Scholar
8. Ringwood, A.E., Kesson, S.E., Ware, N.G., Hibberson, W.D. and Major, A., “Immobilization of High-Level Nuclear-Reactor Wastes in Synroc” Nature 219, 278 (1979).Google Scholar
9. Lutze, W. and Ewing, R.C., “Summary and Evaluation of Nuclear Waste forms”, Radioactive Waste forms for the Future,” eds. Lutze, W. & Ewing, R.C. (North-Holland, 1988) 699–740.Google Scholar
10. Grambow, B., “The Role of Metal Ion Solubility in Leaching of Nuclear Waste Glasses,” Scientific Basis for Nuclear Waste Management V, ed. Lutze, W. (Elsevier, MRS Proceedings, vol. 11, 1982) pp. 93–102.Google Scholar
11. Chick, L.A. and Pederson, L.R., “The Relationship Between Reaction Layer Thickness and Leach Rate for Nuclear Waste Glasses,” Scientific Basis for Nuclear Waste Management VII, ed. McVay, G.L. (Elsevier, MRS Proceedings, vol. 26, 1984) pp. 635–642.Google Scholar
12. Grambow, B., “A General Rate Equation for Nuclear Waste Glass Corrosion,” Scientific Basis for Nuclear Waste Management VIII, eds. Jantzen, C.M., Stone, J.A. and Ewing, R.C. (MRS Proceedings, vol. 44, 1985) pp. 15–27.Google Scholar
13. Aagaard, P. and Helgeson, H.C., “Thermodynamic and Kinetic Constraints on Reaction-Rates Among Minerals and Aqueous-Solutions. 1. Theoretical Considerations,” American Journal of Science 281, 237–285 (1982).Google Scholar
14. Grambow, B. and Müller, R., “First-Order Dissolution Rate Law and the Role of Surface Layers in Glass Performance Assessment,” J. of Nuclear Materials 298, 112–124 (2001).Google Scholar
15. Sunder, S., Shoesmith, D.W. and Miller, N.H., “Electrochemical Studies of Corrosion of Simfuel: Simulated Used UO2 Fuel,” Scientific Basis for Nuclear Waste Management XVI, eds. Interrante, C.G. and Pabalan, R.T. (MRS Proceedings, vol. 294, 1993) pp. 35–40.Google Scholar
16. Stroes-Gascoyne, S., Johnson, L.H., Tait, J.C., McConnell, J.L. and Porth, R.J., “Leaching of Used Candu Fuel: Results from a 19-Year Leach Test Under Oxidizing Conditions,” Scientific Basis for Nuclear Waste Management XX, eds. W.J. Gray and Triay, I.R. (MRS Proceedings, vol. 465, 1997) pp. 511–518.Google Scholar
17. Wronkiewicz, D.J., Buck, E.C. and Bates, J.K., “Grain Boundary Corrosion and Alteration Phase formation During the Oxidative Dissolution of UO2 Pellets,” Scientific Basis for Nuclear Waste Management XX, eds. Gray, W.J. and Triay, I.R. (MRS Proceedings, vol. 465, 1997) pp. 519–526.Google Scholar
18. Murphy, W.M. and Codell, R.B., “Alternate Source Term Models for Yucca Mountain Performance Assessment Based on Natural Analog Data and Secondary Mineral Solubility,” Scientific Basis for Nuclear Waste Management XXII, eds. Wronkiewicz, D.J. and Lee, J.H., (MRS Proceedings, vol. 556, 1999) pp. 551–558.Google Scholar
19. Miller, M.L., Finch, R.J., Burns, P.C. and Ewing, R.C., “Description and Classification of Uranium Oxide Hydrate Sheet Topologies”, Scientific Basis for Nuclear Waste Management XIX, eds., Murphy, W.M. and Knecht, D.A. (MRS Proceedings, vol. 412, 1996) pp. 369–376.Google Scholar
20. Chen, F., Burns, P.C. and Ewing, R.C., “79Se: Geochemical and Crystallo-Chemical Retardation Mechanisms,” Scientific Basis for Nuclear Waste Management XXII, eds. Wronkiewicz, D.J. & Lee, J.H. (MRS Proceedings, vol. 556, 1999) 1115–1122.Google Scholar
21. Ewing, R.C., “Natural Glasses: Analogues for Radioactive Waste forms,” Scientific Basis for Nuclear Waste Management, vol. 1, ed. McCarthy, G. J. (Plenum, 1979) pp. 57–68.Google Scholar
22. Weber, W.J., “A Review of the Current Status of Radiation Effects in Solid Nuclear Waste forms,” Scientific Basis for Nuclear Waste Management VI, ed. Brookins, D.G. (Elsevier, MRS Proceedings, vol. 15, 1983) pp. 407–414.Google Scholar
23. Weber, W.J. and Ewing, R.C., “Radiation Effects in Crystalline Oxide Host Phases for Immobilization of Actinides,” Scientific Basis for Nuclear Waste Management XXV, eds. McGrail, P. and Cragnolino, G.A. (MRS Proceedings, this volume).Google Scholar
24. Lumpkin, G.R. and Ewing, R.C. “Alpha-Decay Damage and Annealing Effects in Natural Pyrochlores: Analogues for Long-Term Radiation Damage Effects in Actinide, Pyrochlore, Structure Types,” Scientific Basis for Nuclear Waste Management XII, eds. Lutze, W. and Ewing, R.C. (Materials Research Society Proceedings, vol. 127, 1989) pp. 253–260.Google Scholar
25. Weber, W.J., Devanathan, R., Meldrum, A., Boatner, L.A., Ewing, R.C. and Wang, L.M., “The Effect of Temperature and Damage Energy on Amorphization in Zircon,” Microstructural Processes in Irradiated Materials, eds. Zinkle, S.J., Lucas, G.E., Ewing, R.C. and Williams, J.S. (Materials Research Society Proceedings, vol. 540, 1999) pp. 367–372.Google Scholar
26. Wang, S.X., Wang, L.M., Ewing, R.C. and K.Kutty, V.G. “Ion Irradiation Effects for Two Pyrochlore Compositions: Gd2Ti2O7 and Gd2Zr2O7” Microstructural Processes in Irradiated Materials, eds. Zinkle, S.J., Lucas, G.E., Ewing, R.C. and Williams, J.S. (MRS Proceedings, vol. 540, 1999) pp. 355–360.Google Scholar
27. Sagüés, A.A., “Nuclear Waste Package Corrosion Behavior in the Proposed Yucca Mountain Repository,” Scientific Basis for Nuclear Waste Management XXII, eds. Wronkiewicz, D.J. and Lee, J.H. (MRS Proceedings, vol. 556, 1999) pp. 845–854.Google Scholar
28. Werme, L.O., “Fabrication and Testing of Copper Canister for Long Term Isolation of Spent Nuclear Fuel,” Scientific Basis for Nuclear Waste Management XXIII, eds. Smith, R.W. and Shoesmith, D.W. (MRS Proceedings, vol. 608, 2000) pp. 77–88.Google Scholar
29. Pigford, T.H. and Chambré, P.L., “Near-Field Mass Transfer in Geologic Disposal Systems: A Review,” Scientific Basis for Nuclear Waste Management XI, eds. Apted, M.J. and Westerman, R.E. (MRS Proceedings, vol. 112, 1987) pp. 125–141.Google Scholar
30. Conca, J.L., Apted, M. and Arthur, R., “Aqueous Diffusion in Repository and Backfill Environments,” Scientific Basis for Nuclear Waste Management XVI, eds. Interrante, C.G. and Pabalan, R.T. (MRS Proceedings, vol. 294, 1993) pp. 395–402.Google Scholar
31. Ewing, R.C., Tierney, M.S., Konikow, L.F., Rechard, R.P., “Performance Assessments of Nuclear Waste Repositories: A Dialogue on Their Value and Limitations,” Risk Analysis 19, 933–958.Google Scholar